| ID Number | Title of the concept / technological information | Topic | Name of the representative | Summary of information | |
|---|---|---|---|---|---|
| 1 | 31 | Method of dismantling and prior water stoppage work for RPV | B-1 | 個人(所属無し) | (IRID reference translation) First Part Method of prior water stoppage work for PCV Second Part Dismantling method of RPV Third Part Debris removal from dismantled waste material |
| 2 | 33 | The Plan “MOGRA”: the treatment of damaged nuclear fuel of Fukushima Daiichi Nuclear Power Station | B-1 | The consulting room for the radiation, Yukio Sumida | Basically the geological disposal technology is applied for the damaged nuclear fuels(DNF).The access from the upper direction of nuclear power station(NPS), is not effective because of high radiation level. The access from the lower of NPS is better than above . Around NPS, several vertical holes are dug. The horizontal holes are dug at the branch of the vertical and they can approach the NPS. The radiation level is measured at the planning points and the form of DNF is evaluated based on the code. After evaluating the form of DNF, the “core catcher” is carried into the horizontal hole. The damaged nuclear fuels are fallen into the core catcher.It is carried out . DNF are treated by the pyroprocessing or the wet reprocessing method. |
| 3 | 34 | removal of the ionic contaminations | B-2 | Hideaki Narusawa | (IRID reference translation) Using polyphosphoric acid, collect by chelate polyvalent metal ion contained in reactor cooling water. React collected liquid with calcium, and precipitate it as an apatite to separate. Concentration of supernatant radioactive material should be decreased remarkably. Decrease radioactive material concentration of reactor cooling water by repeating this process and enhance safety of operation. |
| 4 | 35 | (IRID reference translation) Introduction of shielding material for internal investigation and fuel debris removal | B-2 | O&K Trading Co., Ltd. | (IRID reference translation) We currently are developing four types of shielding material. Features of those products are as follows. 1. KRAFTON-XP series: Gamma-ray shielding material Three types of products has already been developed and those specific weights are; 3.2, 5.2, 7.2. Principle use: lining of emergency shelter for the workers of decontamination operation in Fukushima etc. 2. KRAFTON-XF series: Gamma-ray shielding material Two types of products has already been developed and specific weights of those are 3.2 and 7.2 respectively. The difference from KRAFTON-XP above is flexibility of quality of material. Principle use: Shielding for air dose at the decontamination site. 3. KRAFTON-N: Neutron shielding material Thickness required for 1/10 value layers for neutron ray: about 15.0cm Principle use: neutron protective screen. 4. KRAFTON-C1: Neutron shielding material (transparent color) Thickness required for 1/10 value layer for neutron ray: about 15.0cm Principle use: Window for hot cell, Chemical reconnaissance vehicle for Self-Defense Force. |
| 5 | 36 | Technologies for shielding fuel debris in reactor and removal from top of PCV in atomosphere. | B-2 | Iwao Umeda | ① Previous to removal of fuel debris from RPV/PCV, it is necessary for protecting wokers from radiation. For this purpose, technology of shielding by pre-packed pyrite ore heavy concrete around RPC, between RPC and PCV, and bottom of PCV. ② Shielding container consists of double cylinders for fuel debris retrieval and technology of iron scale shielding mixed fuel debris for removal debris in reactor from top of PCV in atomosphere. |
| 6 | 37 | (IRID reference translation) Direction of Final Disposal including Topic A･B and Meltdown (Proposal) | A-1 | 酒井商店 酒井岩男 | (IRID reference translation) ○If the program period in decommissioning road map is acceptable, we would like to promote final disposal method by covering surrounding area of Fukushima NPS with soil. See accompanied supplementary document. ○Although it is appropriate to promote verification and practical use of RFI topic A･B (important element) at this point, practicability of development is uncertain and････considering the fact that time and cost is not appropriate even if it is feasible and there will be problems caused in usage (investigation/correspondence is not decided). Therefore, in Phase 2 selection step, we would like to propose concurrent implementation incorporating final disposal (decommissioning and management) into the plan. ○Possible disposal site in that case includes five places which are the space, ground surface, shallow and deep embedding, and deep ocean floor. Considering the environmental situations such as air/sea current and movement of crustal plate, ”Deep embedding method”” Buried valley plan” in the most stable condition may be effective. |
| 7 | 38 | Principal technical solution of BNPS application (excluding the human factor) | B-2 | MedProFarm Ltd. | Biosafe Nanocomposite Polymer Sorbent (BNPS) consiscts of Polymer mixture (A) and Catalytic mixture (B) and it could be packed in the hermetic plastic box. Parts A and B are divided in the box by the thin hermetic film (from polyethylene, for example). When necessary, open the box, break the film membrane and mix vigorously parts A and B. Then the resulting final mixture put into the toxic (radioactive) water with fuel-debris. Wait 30 minutes for gelation of the total water with fuel debris. Thus, no leaks no troubles with water and fuel-debris retrieval (topic B-2 ) Then for reducing the volume you can to evaporate water at 600C for not less than 48h or separate water under the vacuum (for membrane with pore d=100mkm and vacuum about 0.1atm the time about 6 h). |
| 8 | 40 | Removal of nulear debris by laser cut small segment transport method | B-2 | Allied Lasers,Inc. Takashi Arisawa | Laser beam can be focused down onto the surface of materials at high energy intensity over TW/cm2.This method is widely applied to the micro processing of ceramics,metals ,etc. Although minute area is the procssing area, this process can be easily multiplied by longterm remote working capability, which can extended to the large drill hole creation by ocnstant removal of laser cut devris like as a onion pealing. This hole is available for the large volume removal in the 2nd step.This method can be realized by enhancing the fiber based laser system. We also have to remind the advantage of very low secondary nuclear waste. |
| 9 | 41 | Discharge of debris by armor vehichle with heavy shielding | B-1 | Tadashi Inoue; Research Advisor to CRIEPI | (IRID reference translation) Surround Units 1 to 4 with hot cell, and attack reactor core portion by armored car equipped with shielding glass in front, back, right and left sides. Armored car is equipped with the sensors (such as temperature and radiation intensity), and each device is equipped to be attachable to the front of the car (metal cutter, catching jig etc.). In parallel with the development of this armored car, construct hot cell, dismantle the Unit No.4 and make the unit to be utilized as a work place to dismantle the remaining three units in order of Units No.3, 2, and 1. Debris transferred to the site of Unit No. 4 will be stored in the storage container and carried out in order. |
| 10 | 42 | Fiber scopes, having revolver multi lenses resist to radio active ray | A-2 | Nihon Sanmo Dyeing Co., Ltd. | The new apparatus is proposed for solution to the disability of inside observation of PVC/RPV by means of glass fiber camera. To prepare for the black out of lens, here proposed multi lens equipped on the revolver disk. The multi lens equipped scope might be enable to stretch observation time more, just related to the number of lenses. Revolver case should be covered by shield materials resistive against radio activity. |
| 11 | 43 | (IRID reference translation) Removal Methods of Radiation Shielding and Fuel Debris by freezing Interior of PCV with Ice | B-1 | 坂巻 正健 | (IRID reference translation) To prevent contaminated water leakage and migration of contaminants, fix PCV internals, make a protection against radiation, and conduct excavation and removal of fuel debris partially in the air, put low temperature ice inside the PCV and freeze overall unit internal. 【Expected procedures】 (1) Put low temperature spherical ice to replace cooling water into the bottom of PCV to cool down fuel debris. (2)Put spherical ice into vent pipe as well as S/C internal through the bottom of the PCV and prevent leakage of contaminated water by freezing the leakage holes. (3)Put ice into nuclear reactor and underground of turbine building and to freeze them. Reduce dose of underground radiation by removing and exchanging the contaminated water partially. (4)Identify and repair damaged portion of vent pipe, S/C, and bottom of the PCV. After that, make a protection against radiation by throwing the ice from the bottom to top of PCV, and repair damaged portion of PCV. (5) Freeze overall PCV internal, and dig a shaft and excavate ice, PCV internals, and fuel debris partially in the air at the same time, and take them out. Store the ice, internals, and fuel debris in the storage container at the top of the shaft. |
| 12 | 44 | Safe long term embedding of fuel debris for sorage and disposal | B-2 | Johannes Fachinger; "Furnaces Nuclear Applications Grenoble FNAG" | Waste (fuel debris) is mixed with graphite & inorganic glass binder and solidified through compression (1.000 bar) & heating (up to 1.100 °C) in a HIP vessel. Up to now successful tests have been done with inactive simulants for mixed debris loading. This test proved a wide varibalitiy of the IGM Matrix for different waste types. The product is nearly pore free and corrosion resistant, resulting in excellent leaching resistance (see attached file figure 1 Waste containers up to approx. 200 L may be produced. OPTION: to surround the debris containing IGM by a shell radioactivity-free IGM, by filling a prefabricated IGM shell with zeolite/IGM mixture prior to HIP. |
| 13 | 45 | IGM for solidifcation of fuel debris | B-2 | Furnaces Nuclear Applications Grenoble | IGM is an FNAG development to embed radioactive waste for long term safe storage and final disposal. The waste (fuel debris) is mixed with graphite & inorganic glass binder and solidified through compression (1.000 bar) & heating (up to 1.100 °C) in a HIP vessel. Up to now successful tests have been done with inactive simulants for mixed debris loading. The fuel debris can be inserted without prior treatment into the IGM. May be a size reduction is necessary for very large parts (> 200 mm).The product is nearly pore free and corrosion resistant, resulting in excellent leaching resistance (see attached file 1). Waste containers up to approx. 200 L may be produced. As option the debris containing IGM can be surrounded by a shell radioactivity-free IGM. |
| 14 | 46 | (IRID reference translation) Underground Nuclear Testing | B-1 | Anonymous | (IRID reference translation) Using energy of nuclear explosion under the ground, promote nuclear fission reaction in nuclear fuel and reduce scatter of radioactive material from current value. Isn’t it easy to take out fuel debris in several years? |
| 15 | 47 | Development of a subcriticality surveilance syatem for fueldebris retreaval | A-1 | Yoshitaka NAITO NAIS co. inc | (IRID reference translation) Fuel debris removal is required to be conducted under subcritical condition. Now, monitoring of temperature of cooling water and noble gas (Xe135) is employed as a method of subcritical check. However this method requires estimated absolute amount for nuclear fission reaction and its accuracy is low relative to the large amount of labor. We hereby propose the method to monitoring neutron reactivity by the use of huge difference in isotopic ratio between noble gas released from spontaneous fission nuclide Cm (Kr88/Xe135) and the nuclear fission of U and Pu. The important thing in this method is measurement of Kr88. In general Ge-Counter will be used but since production of Kr88 is small and half-life is comparatively short, it requires some adjustment such as shortening the distance between the locations where it is generated and measured, or reducing the background of γ-ray at measurement location etc. Please refer to the Presentation of Atomic Energy Society. |
| 16 | 48 | Ideas to put investigation equipement, such as cameras into the PCV/RPV | A-1 | CH2M Hill | The general strategy is to, following the investigations of the PCV and RPV, leave the biological shield in a condition such that minimum work is required to seal it sufficiently to hold water. While “open air” methods of fuel retrieval may be attempted, these methods may be unsuccessful and thus, as a backup, the possibility to flood the PCV should remain. This being said, existing penetrations, modified as necessary, should be used when feasible. These existing penetrations have a seal weld between the Drywell inner wall and the penetration guide tube which may save work should it be required to seal the drywell. |
| 17 | 49 | Innovative Approach to Fuel Debris Removal | B-1 | CH2M HILL | Conceptual Study on Innovative Approaches to Fuel Debris The innovative approach presented here is concerned with accessing and removal of fuel debris from the top side of the PCV/RPV under water. The basic approach is to fill the PCV with grout to a level necessary stop water leakage from the reactor and pedestal area. |
| 18 | 50 | (IRID reference translation) Provision of Shielding Materials for Neutron and Gamma-ray (Transparent・Non-transparent Body) and Development Cooperation | B-2 | 株式会社 RSC(Radiation Shield Consultants) | (IRID reference translation) 1. Shielding material series (1) Neutron shielding (transparent body series): maintains more than 93% of light transmission rate, capable of normal working, and has high heat resistance. (2) Neutron shielding (non-transparent body series): has secondary Gamma-ray suppressibility, and excellent impact resistance performance, and flexible type is available. (3) Gamma-ray shielding material series: capable of cold working and on-site execution, has high impact resistance performance, and flexible type is available. (4) Series of simultaneous shielding material for gamma-ray and neutron (non-transparent body). Features are equivalent to (2) and (3). (5) Structure of simultaneous shielding for gamma-ray and neutron (transparent body) Compound type of transparent neutron and gamma-ray shielding material. 2. Radiation shielding analysis (1) Analysis and evaluation on complex shape shielding. (2) Analysis and evaluation on shielding by composite material. |
| 19 | 51 | Long distance telescopic tube type Power Manipulator(A1000) | B-2 | Mitsui Engineering & Shipbuilding Co., Ltd./Wälischmiller Engineering GmbH (Germany) | We suggest Power Manipulator having the lifting device of the high lift telescope for lift 30m - 40m to apply to the fuel debris retrieval. In addition, superior manipulator to the high handling load and durability that are applicable to various methods of fuel debris retrieval process (mechanical cutting or blowout).The main specifications are as follows. ・Telescope lift ：30m～40ｍ ・Manipulator arm capacity ： 100kg ・Manipulator arm Length ：App.1400mm(Depends on arm capacity ・Axes ：6+Gripper open/close ・Apply for ：Mechanical or Plasma, … cutting ・Radiation proof ：1MGy ・Water proof ：Water proof ・Option ：Arm can exchange remotely by using special device |
| 20 | 52 | Long lift Power Manipulator(Lifting wire type) | B-2 | MitsuiEngineering&Shipbuilding Co.,Ltd./Wälischmiller Engineering GmbH (Germany) | We propose the Power Manipulator lifted up/down by the lifting wire having 30m - 40m stroke to apply to the fuel debris retrieval. In addition, manipulator itself has thesuperior performance, that is the heavy handling load and enough durability which is applicable to various methods of fuel debris retrieval process (mechanical cutting or thermal cutting).The main specifications are as follows. ・Lift of lifting device ：30m～40ｍ ・Manipulator arm capacity：100kg ・Manipulator arm Length：App.1400mm(Depends on arm capacity ・Axes：6+Gripper open/close ・Apply for ：Mechanical or Plasma,…cutting ・Radiation resistance：1MGy ・Water proof：Water proof ・Option：Arm can be exchangedremotely by using special device |
| 21 | 53 | Long lift Power Manipulator with mobile leg (W1000) | B-2 | Mitsui Engineering & Shipbuilding Co., Ltd./Wälischmiller Engineering GmbH (Germany) | We propose the Power Manipulator, together with the outrigger, lifted by the wire having 30 - 40m stroke to apply to the fuel debris retrieval. Manipulator itself has the superior performance, that is the heavy handling load and enough durability which is applicable to various methods of fuel debris retrieval process (mechanical cutting..). Specifications are as follows. ・Lift：30～40ｍ ・Arm capacity：100kg ・Arm Length：App.1400mm(Depends on arm capacity) ・Axes：6, Gripper open/close, Leg---3, Hanging base---2 ・Apply for ：Mechanical cutting ・Radiation resistance：1MGy ・Water proof：Water proof ・Option：Arm can be exchanged remotely by using special device |
| 22 | 54 | (IRID reference translation) Debris removal plan for Fukushima Daiichi NPS | B-1 | Kouji株式会社 | (IRID reference translation) Debris removal plan for Fukushima Daiichi NPS. |
| 23 | 55 | Robotic self-construction platform for smooth robot locomotion and work | B-2 | Rui Fukui (Department of Mechanical Engineering, The University of Tokyo) | (IRID reference translation) Our research group are working on the development of the system that robot on its own configures structures which will be the scaffold where various type of robots are utilized in Fukushima Daiichi NPS. Specifically, we are developing the robot group which transports and constructs the standardized module material and its construction material. This system is characterized by that the robot and construction materials are equipped with multiple mechanical guide structures to enable robots to configure on its own without any help of human operator. This will enable us to minimize the number of sensors and power source used, and it is expected to be operable in the environment with high radiation. This technology allows us to transport manipulator which cannot be operated in the wide range but is handy to the operation site. Also, efficiency is expected to be promoted by separating operation robot and transportation robot in the operation that requires large amount of materials. |
| 24 | 56 | Inovative products that may assist at Fukushima Daiichi | A-2 | John W. Bramblet-Newton Reseach Labs, Inc. | Newton manufactures a number of products that may assist at Fukushima: 1.Nuclear Underwater Laser Scanner to produce CAD models of objects. 2. Bundle Scanner to produce a CAD model and high resolution pictures of fuel bundles as they are removed from the spent fuel pools or reactor (developed in partnership with EPRI). 3. Nuclear Underwater Robots that can carry various sensor packages. These robots are supplied both tethered and in models that operate autonomously; pre-programed and machine vision guided. 4. Underwater Machine Vision Cameras with software that can be used to characterize various objects in a nuclear environment 5. More nuclear products can be found at: www.newtonlabs.com |
| 25 | 57 | (IRID reference translation) Compact Above- and Underwater Submersibles for S/C and PCV investigation | A-2 | SUGIURA MACHINEDESIGN OFFICE "SMD" | (IRID reference translation) SMD is a member of the NPO Japan Underwater Robot Network and developed compact experimental submersible equipped with ballast tank with high steerability for straightness. Installed inside are scintillation-type Geiger counter the submersible, indicator for depth, wired camera for analogue steering by thin cable of carbon Kevlar, and high-definition cameras for recording. We won the first prize for ROV in Underwater Robot Convention by JAMSTEC in 2013. This submersible is characterized by using light-weight plastic hull and its material cost is low, system is not complicated, batteries are mounted inside the submersible, and being capable of hovering at given degree of depth without a thruster since neutral buoyancy is adjustable. Now, TCP/IP communication by two-wire tether is also implemented and it enables high-speed communication by two-wire, and camera signal and radiation data can also be digitalized and sent in real time. |
| 26 | 58 | Mobile Tool Platform to Remove Debris from RPV | B-2 | Konecranes Nuclear Equipment & Services (KNES) | (IRID reference translation) Introducing Technology Development regarding crane manipulator for fuel debris removal. |
| 27 | 59 | (IRID reference translation) Highly-efficient narrow crawler entering narrow space | A-2 | SMD CEO Tomio Sugiura | (IRID reference translation) With our possessed technology such as of vehicle-type crawler robot, multi-legged robot, flying robot, we conduct various types of experiment with installing the actual Geiger counter, image transmission apparatus, and sensor after the devastating accident at Fukushima Daiichi NPS. This information provides concrete samples of radiation measurement using caterpillar type and multi-legged robot which can break into narrow space with rubble and obstacles. |
| 28 | 60 | IRID Conditioning of fuel debris in IGM | B-2 | Wolfgang Diepenbruck | The removal of fuel debris and fuel from the RPV and the PCV will produce huge amounts of high active waste. A newly developed matrix, the Impermeable Graphite Matrix IGM, offers unique advantages: no radiolysis, no loss of voalatile radionuclides, good volume reduction, excellent leaching stability, excellent heat dissipation, not affected by chloride. the industrially well established Hot Isostatic Pressing (HIP) process will be applied, needs adaptation to the high active environment. |
| 29 | 61 | (IRID reference translation) Observation of environment radiation by wheel type lock Crawler | A-2 | 有限会社杉浦機械設計事務所 | (IRID reference translation) We obtained certain observation results from the Radio control car of 1/4-scale lock crawler equipped with scintillation-type Geiger counter. |
| 30 | 62 | (IRID reference translation) Observation of environment radiation by a flying robot | A-2 | 有限会社杉浦機械設計事務所 | (IRID reference translation) We obtained results from the experiment of automatic flight with using GPS and FPV flight by four-rotor and six-rotor flying robot. We already have started to work on plant deterioration investigation with major manufacturer. |
| 31 | 63 | Long reach type Power Manipulator(TELBOT) | A-1 | Mitsui Engineering & Shipbuilding Co., Ltd./Wälischmiller Engineering GmbH (Germany) | We would like to propose Manipulator with long reach arm (TELBOT) to apply for handling inspection devices (ITV etc.) in the PCV and RPV. Each joint of the arm rotates endlessly and thanks to the long reach and slim arm, it can access into narrow target spaces. Furthermore, this arm consists of A: the arm link and joints part (mechanical part) and B: the motor drives parts (electric part). This is one of the big advantages against the radiation environment. We can provide intelligent and intuitive operating system JOYARM. Specifications are as follows. ・Manipulator arm Length：App. 5ｍ(Depends on arm capacity) ・Manipulator arm capacity：5kg～10kg(Depends on arm length) ・D.O.F.Arm：8 ・Apply for ：Remote operation ITV and other tools in reactor ・Radiation proof：1MGy |
| 32 | 64 | (IRID reference translation) Conceptual study for alternative construction method for fuel debris removal | B-1 | 池見慎一 | (IRID reference translation) Accident at Fukushima Daiichi NPS is fundamentally different from the nuclear accident at Three Mile Island. In the case of latter accident, there were fuel debris in the pressure vessel, and those were not leaked into containment vessel, but those of the former diffused to not only the pressure vessel but also to the containment vessel. Even if fuel debris can be removed by drilling a hole on the pressure vessel, I think it is impossible to detect and remove fuel debris that had fallen into the containment vessel. This is because the rack that supports pressure vessel and the driving unit of fuel rod will interfere with insertion and transportation of measurement equipment and it will take a lot of time and cost that we cannot imagine. Therefore, the best way of transporting fuel debris is to cutoff the fuel debris that had fallen under the bottom of pressure vessel, driving unit, supporting rack, containment vessel, and remove those. Also, artificial island on the sea is required to be constructed to bury the radioactive wastes that are removed. |
| 33 | 65 | Surface Corium Removal Head | B-2 | SimplyInfo.org Research Team | A novel cutting cutting head design to remove fuel debris residue from surfaces inside or outside containment . The cutting head tool would be ideally suited for dislodging these small residue debris formations as have been seen on containment scope inspections. This cutting head could be used with various debris collection techniques including pumped removal or catchment as needed. |
| 34 | 66 | (IRID reference translation) Development of reactor grade catheter and high load manipulator | B-2 | KYB(株) 技術本部 基盤技術研究所 | (IRID reference translation) 1. Contents of technology (characteristics, specifications, and performance) ･Manipulator technology characterized by compact, high speed, high density, high rigidity, and high-accuracy. Also it utilizes environmental-responsive type water pressure drive control technology (Aqua-Drive-System: called ADS) with using “fresh water” for working fluid to reduce radiation-contaminated waste as much as possible. ･Drive and control technology for heavy machine specialized in the transportation and remote control of underwater testing equipment (imaging camera head, work tool etc.) by high-accuracy servo control using servo valve with hydraulic drive and hydraulic technology that supports debris removal. ･Specifications: maximum working fluid pressure of 14MPa, and minimum working pressure of 0.25MPa (equivalent to the pressure of water service piping networks). Output 2.5-100kw. ･Our company has general purpose valve of ADS equipment(water pressure equipment) that consists of these technology: control valve, such as fluid pressure, flow rate, direction of water pressure pump, motor, cylinder, servo valve, proportional valve as well as development capability for more smaller and larger type equipment. ･Automatic remote control. |
| 35 | 67 | Visualization technology of the position and shape of the dropped fuel debris using cosmic rays muon | A-2 | Engineering Advancement Association of Japan, Geo-space Engineering Center | The three-dimensional position of the dropped fuel debris can be estimated from processing cosmic ray muons. Muon penetrates material because of a high energy elementary particle. A part of muons is absorbed by interaction with the material. We can estimate the internal structure of an object measuring the absorption properties of the muons. The position and quantity of the dropped fuel from the internal structure of the reactor can be visualized by measuring in the surrounding ground of the damaged Fukushima Daiichi nuclear reactor and applying the three dimensional geotomography. Underground part of the reactor can be measured from a trench excavated around the nuclear reactor. It is possible to apply these techniques to accurately determine the shape and position of any fuel debris. |
| 36 | 68 | (IRID reference translation) Withdrawal from the underground, “Method of sarcophagus/water sarcophagus” | B-1 | Yuji Miyake professional engineer | (IRID reference translation) This method can be achieved safely in short term because this is to access from the underground by establishing sarcophagus from the bottom of water sarcophagus. Since the points of access and removal for upper side by water sarcophagus are located on opposite sides, operations can be performed in parallel, and this is multiple-layered method. If we access from underground, we can safely approach within 60 cm from melting fuel instead of 35m. Melted fuel may lie in the layer under the foundation. Since debris was fused and melted down by its own weight, we can find those within the shortest distance if we access just below those fuel. If we drill an inspection hole from the bottom, we can safely perform an excavation by searching with temperature/radiation sensor. Also, we can conduct our operation without having an impact of radiation because we inject mortar from the bottom and monitor by using a periscope. Since this operation needs to encounter melted fuel directly, remote control by unmanned machine is required. Since we use remote hydraulic control for an operation at close range in place of an electronic control, we can maintain reliability. |
| 37 | 69 | (IRID reference translation) Element technology for withdrawal from the underground, “Method of sarcophagus/water sarcophagus” | B-2 | Yuji Miyake professional engineer | (IRID reference translation) This method can be achieved safely in short term because this is to access from the underground by establishing sarcophagus from the bottom of water sarcophagus. Since the points of access and removal for upper side by water sarcophagus are located on opposite sides, operations can be performed in parallel, and this is multiple-layered method. If we access from underground, we can safely approach within 60 cm from melting fuel instead of 35m. Melted fuel may lie in the layer under the foundation. Since debris was fused and melted down by its own weight, we can find those within the shortest distance if we access just below those fuel. If we drill an inspection hole from the bottom, we can safely perform an excavation by searching with temperature/radiation sensor. Also, we can conduct our operation without having an impact of radiation because we inject mortar from the bottom and monitor by using a periscope. Since this operation needs to encounter melted fuel directly, remote control by unmanned machine is required. Since we use remote hydraulic control for an operation at close range in place of an electronic control, we can maintain reliability. |
| 38 | 70 | Advanced Technology of High Radiation Hardening Electronics System | A-2 | Marubeni Utility Services, Ltd./Ermes (France) | Products, Technology, Compact Technology, etc. for CMOS Camera, 3D Camera, Radiation Source Survey System, Geometric Measurement System, Dose Measurement, Electronics Modules(Encoder etc.), Data Transmission System, Motor, Battery Management System, etc. Please refer to "File 1" and "File2". |
| 39 | 71 | Advanced Technology of High Radiation Hardening Electronics System | B-2 | Marubeni Utility Services, Ltd./Ermes (France) | Products, Technology, Compact Technology, etc. for CMOS Camera, 3D Camera, Radiation Source Survey System, Geometric Measurement System, Dose Measurement, Electronics Modules(Encoder etc.), Data Transmission System, Motor, Battery Management System, etc. |
| 40 | 72 | (IRID reference translation) Concept of fuel debris removal without flooding by alternative shield | B-1 | 富士電機株式会社、清水建設株式会社、株式会社ビージーイー(英国Cavendish Nuclear社) | (IRID reference translation) This is an alternative method for the case where complete flooding cannot be maintained. This proposal is the concept idea to remove fuel debris, and dismantle the reactor structures in the gas atmosphere with securing shielding function that can substitute for water, and provides information based on the verification of decommissioning of Tokai Nuclear Power Plant and actual results of England. 1) Load shielding material inside the PCV/RPV and shield direct radiation from fuel debris, then 2) Set up shield (rotating plug method) on the operation floor and install mast and manipulator unit. 3) Dismantle the reactor structures (including residual debris in RPV) in order from top to bottom. 4) After removing structures of upper side, put debris at the bottom of PCV mixed with shielding material in the monitoring storage for a certain period of time if necessary. 5) Put Remotely Operated Vehicle (ROV) to the bottom of PCV from upper side and horizontal side and dismantle the shielding material and debris in order to improve efficiency for removal of debris at the bottom. |
| 41 | 73 | (IRID reference translation) Remote dismantle technology for nuclear reactor in air. (GCR) | B-2 | 富士電機株式会社、清水建設株式会社、株式会社ビージーイー(英国Cavendish Nuclear社) | (IRID reference translation) This proposal provides information on the key technology regarding remote dismantle method that can be expected to be used for the removal of fuel debris and reactor structure in air. This information is based on the actual results of decommissioning at Tokai Nuclear Power Plant, performance in UK, and Qualification test performed for government. 1) Rotating shielding plug: This is expected to be a compensating shielding when flooding of PCV cannot be achieved. 2) Large type mast arm: Combining with the technology of 1), this can remotely perform a series of actions including positioning, holding and cutting of the reactor object within the diameter of about 20m. 3) Jacking down method: Capable of cutting and demolition of reinforced-concrete structure remotely by lowering the operation stage. 4) Utilizing Remotely Operated Vehicle (ROV): This can be possible access tool from the side of PCV, and has many operating experiences in the Nuclear Power facilities oversea. |
| 42 | 74 | Area A2: Measurement of fuel debris in a high gamma radiation environment (activation foil) | A-2 | NUKEM Technologies GmbH | Nuclear fuel or fuel debris can be identified by its neutron emission from spontaneous fission or (alpha,n) processes. A method to detect this is the use of foils with easy to activate isotopes like gold, which are used to cover the area of interest. After the exposition time the activated isotopes can locally be measured at the foil at a clean laboratory room (with no background radiation) by use of gamma spectrometers or by mass spectroscopic methods. |
| 43 | 75 | Area B2: Measurement of fuel debris and activated material in a high gamma radiation field for sorting | B-2 | NUKEM Technologies GmbH | For the sorting of the material from RPV or PCV, the monitor FAMOS as designed by NUKEM is the ideal device. It can be operated under water and measures the neutron and gamma emission of material collected with a basket, which then can be immediately sorted. The monitor can distinguish between nuclear fuel (which has been burned up partly), activated material (i.e. structural parts of fuel elements etc.) and other material. |
| 44 | 76 | Area A2: Localisation of fuel debris by temperature measurement in high radiation gamma fields (temp | A-2 | NUKEM Technologies GmbH | A method to localise nuclear fuel is the detection of the released decay energy by measuring the temperature with a fibre optical method (fibre Bragg grating). If the measured position is thermally isolated (i.e. using a cover), the temperature increase can be measured and the released energy can be determined. These measurements are not influenced by local high dose rate gamma fields, there is no need for electronics in the measurement area and the fibre can be operated very easily. |
| 45 | 77 | Area A2: Localisation of fuel debris by measurement with fission chambers in high radiation gamma fields | A-2 | NUKEM Technologies GmbH | For the detection of nuclear fuel, the measurement of neutron emission by detectors with low gamma sensitivity is an ideal method, because of the high gamma background. Therefore fission chambers, which are covered by moderator material to increase the sensitivity, are the best choice. Measuring at different points can provide a map of fuel distribution. |
| 46 | 78 | Area A2 - Measurement preparation with the resealable borehole method | A-2 | NUKEM Technologies GmbH | Development of a method for investigation of areas with very high dose rates without the necessity of accessing these areas themselves. With a remote controlled vehicle equipped with special bore and handling tools boreholes can inserted in wall or floor elements. These boreholes will be used for inserting special measurement tools. The measurement tools will analyse the situation inside this areas and searching for fuel debris elements |
| 47 | 79 | RadBall | A-2 | National Nuclear Laboratory Ltd. | The Radball is a 140 mm (5½”) diameter deployable, passive, non electrical gamma hot-spot imaging device that offers a 360 degree view of the deployment area. The device is particularly useful in instances where the radiation fields inside a nuclear facility are unknown but are required in order to plan a suitable nuclear decommissioning strategy. |
| 48 | 80 | Area A 2 -Endoscopic measurement tool development | A-2 | NUKEM Technologies GmbH | Development of endoscopic measurement tools for investigation in not accessible areas (very high dose rate areas). The measurement tools will insert into this areas through special boreholes in walls, floors etc.. The measurement results are necessary for locating the fuel debris particles and for planning further activities. |
| 49 | 81 | Area B1 - Remotely controlled removal of fuel debris | B-1 | NUKEM Technologies GmbH | Molten fuel particles will be spread in a wide field of the nuclear facility. An effective method for removal of these particles is the comminution of big debris accumulations. Therefore a special cutting technology must be developing which will comminute debris accumulations, sucking the manageable parts and storing these parts in storage container. The filled storage container will be removed out of the power plant building. All activities will be done remote controlled. |
| 50 | 82 | Sonar Mapping | A-2 | National Nuclear Laboratory Ltd. | NNL have experience in the underwater profiling of highly active wastes. At Sellafield this has been achieved by deploying a scanning SONAR head into the hostile environment on the end of a pole. The resulting scans can be analysed to provide volumetric measurements of the solid wastes present. NNL worked with James Fisher Nuclear Ltd to deliver the solution for Sellafield Ltd. James Fisher Nuclear Ltd has also deployed a SONAR into other nuclear facilities. |
| 51 | 83 | PCV/RPV Alternate Access and Inspection | A-1 | Jeffrey L. Stevens, The Babcock and Wilcox Company | Adapting techniques used successfully at Three Mile Island, access to the PCV and RPV can be accelerated. Using data acquisition technology from TMI, information vital to planning removal of fuel and core debris can be obtained. Included in this concept are use of a boring machine based on the TMI "core bore" to obtain access prior to sealing and flooding the cavity. Proposed inspection techniques include location of core material using gamma peaks from low volatile fission products and cosmic ray muon imaging. |
| 52 | 84 | Submersible Robotic Systems to Maintain Pool Clarity, Remove Fines, Reduce Dose | B-2 | B&W - Jeffrey L. Stevens | Babcock and Wilcox (B&W) responds with complementary systems to both IRID Topics: A. Robotic Tooling/Cameras for PCV/RPV Access and Characterization – covered elsewhere B. Submersible Robotic Systems to Maintain Pool Clarity, Remove Fines, Reduce Dose See B&W Submission 2.1 from Upload file 1 for graphics |
| 53 | 85 | Corium Location by Muon & Fission Counter, Air-Cool & Removal with Heatpipes | A-1 | Kazutake IMANI,PhD | Since the corium is in RPV and RCV, the location is to be detected by a space muon radiography scintillators ouside the reactor pit and fission counter (in a sensor assembly with temperature detector, microwave guide and self-power gamma doser), and the latter counter is used to prevent the criticality. The corium location at PCV bottom is to be detected by a space muon radiography with 2 scintillators ouside the reactor pit and fission counter. The fuel debris dissipated in RPV can be visuallized by only one new scitillator with 1.5 m long lead collimator. The neutron flux distribution at the core zone and bottom in RPV can be measured by only one long fission counter with the solenoid anode. |
| 54 | 86 | Corium detection by fission counter, self-powered g ray and micro-waveguide | A-2 | Kazutake IMANI,PhD | For the location of corium, the sensor assembly is introduced with microwave guide, ultrasonic horn, fission counter, self powered gamma detector. In order to measure spontaneous neutron flux distribution from the corium inside the pressure vessel, by installing the solenoid to the anode of the long fission counter, it is possible by the delay of the pulse. Another short FC for BWR and FBR can be used for the neutron flux at the corium, and this can also be used for the criticality prevention. A self-powered gamma radiation dosimeter is employed for the high gamma-ray dose. As a crystal resonator of the microwave, we developed new oscillator with highly directional in 700 MHz fundamental frequency, when placed in the reactor with the long waveguide, the the bottom corium is observable. |
| 55 | 87 | A debris removing device employing bubble induced by CO2 laser and a method for the device to access | B-2 | Japan Drilling Co., Ltd. Kawasaki Heavy Industries, Ltd. | CO2 laser has a wavelength with a high liquid absorption rate. The proposed technology employs bubbles induced by irradiating CO2 laser in water, even in opaque water. This technology requires no injecting pressured gas or water for removing molten materials, facilitating a removal of the debris. Irradiating CO2 laser induces a cone-shaped bubble in opaque water. The cone-shaped bubble allows a laser beam to travel inside. The laser beam reaches and interacts with materials underwater before the bubble collapses. The collapse pressure of the induced bubbles causes to eject molten materials from a cavity generated in the materials underwater. Targeted specification: no less than 50m transmitting distance of CO2 laser, Holder: Japan Drilling CO., Ltd |
| 56 | 88 | Fuel corium air cooling by heatpipes and gamma shield by lead alloy pebbles | B-1 | Kazutake IMANI,PhD | Long heatpipes are used to approach to the fuel debris from RCV top as well as the side and bottom. The heatpipe has circular fins to collect the residual energy, and lead pebbles are connected well thermaly to the bottom. Another heatpipe is inserted to the fuel corium hole, where lead alloy is fused at approximately 200 ℃. Since the heatpipe has also air-cooled fins, this can heat-transfer about 100 times of a conventional copper. This heatpipe of the 9 cm2 cross section and 40 m length can transfer approximately 3 kW. When 20 heatpipes are used, the 70 ton debris is cooled by the thermal analysis. As the gamma ray shield of corium at PCV bollom, the lead alloy pebbles can be used to insert the heatpipe. The transparent lead glass contains 70% lead oxide, and this can cut 97% gamma ra |
| 57 | 89 | Technique for PCV/RPV penetration for investigation with remotely operated high speed core boring | A-2 | Taisei Corporation | Establishing new through hole for internal PCV/RPV investigation, remotely operated technique for making opening is required. A new method of high speed dry core boring (Eagle core) modified into remote operation enables this. Conventional core boring cuts with diamond grain, while Eagle Core uses large diamond tip. For this reason Eagle core enables high speed concrete and steel simultaneous cutting. Now this is the highest speed dry core boring. Eagle core was applied at WAK in Germany. Specification of the equipment is shown below. ・Boring depth 2,400 mm ・Boring diameter φ35～152 mm ・Dry air cooling, water cooling is also applicable ・Boring both in air and underwater ・Test data Plain concrete(t=500mm)：60sec Steel plate(t=20mm)：180sec |
| 58 | 90 | Corium retreaval by heatpipe and air-cooled cask | B-2 | Kazutake IMANI,PhD | Manipulator system of parent-child type is mounted on the space station ISS with a two modes of child arm precision control and parent arm coarse. To dismantle safely radioactive corium in the nuclear reactor facility, 3D laser cutter with 5kW carbon dioxide laser has been developed. It is possible that after dissolving implanted lead alloy at 200 ℃ low melting point into the corium hole, and inserting a heat pipe, and after cooling in the small block corium and removed corium by the heat pipe. The residual heat generation of fuel corium that has moved to the caskis removed by heat pipe with air cooling fins. Because F1#3 core contains MOX fuel with Pu, the neutron criticality is to monitor by the fission counter. |
| 59 | 91 | Fuel debris retrieval with remotely operated high speed core boring | B-1 | Taisei Corporation | In accessing and removal of fuel debris from lateral side of PCV/RPV, remotely operated technology for making opening is required. A new method of high speed dry core boring (Eagle core) modified into remote operation enables this and also crushing fuel debris. Conventional core boring cuts with diamond grain, while Eagle Core uses large diamond tip. For this reason Eagle core enables high speed concrete and steel simultaneous cutting. Now this is the highest speed dry core boring. Eagle core was applied at WAK in Germany. Specification of the equipment is shown below. ・Boring depth 2,400 mm ・Boring diameter φ35～152 mm ・Dry air cooling, water cooling is also applicable ・Boring both in air and underwater ・Test data Plain concrete(t=500mm)：60sec Steel plate(t=20mm)：180sec |
| 60 | 92 | Radiation resistant image fiber scope and illumination guide for visualization support system | A-1 | Fujikura Ltd. | Fujikura's fiber scope with silica glass image fiber has high radiation resistant characteristics. This fiber scope system allows for the good visual observation under high radiation environment. This image fiber scope has long and thin cable structure which is supperior to access into a narrow pipe and tight feedthrough. |
| 61 | 95 | Development of Main Inspection Tool with End Effectors for Locating and Removing Waste | B-1 | Southwest Research Institute (SwRI) | Develop inspection tool with end effectors for application from the top of RPV. The tool will be able to telescope down approximately 27-30m and carry end effectors including cameras for locating and observing waste, water jet cutter to cut through the bottom of the RPV to gain access to the debris on the floor of the PCV, a welding device to weld lifting lugs to the bottom of the RPV for removing pieces cut by the water jet, and a grabber unit to pick up and remove the waste. SwRI has previously developed and deployed large telescoping mechanical systems mounted to the top head flange for ISIs. SwRI has designed and fabricated a gripper end effector with stereo vision capability for retrieving waste from a storage tank using the light duty utility robot at the Hanford Waste Tank Farm. |
| 62 | 96 | (IRID reference translation) Stuck Fall Prevention for Unit 1 & 2 | B-2 | Testuro Tsutsui, Organization of Plant Engineers | (IRID reference translation) 1. Identification of defective point Now there are five broken portions and three deformed portions on the exhaust pipe (overall height of 120m, cylinder radius of 3.2m) of the steel tower for Unit No.1 / 2 which are located at 66m from the ground. If this exhaust pipe breaks and its tip end portion falls into the building of Unit No.1 or No.2, and destruct spent fuel pool, it leads to a release of large amount of radioactive contaminant. Therefore we suggest installing a safety wire so that the object can fall to the yard side (the west side＝land side) instead of building side (The east side = sea side), if it collapses. 2. Countermeasures As shown in attached Fig.1, stretch the safety wires in the three directions so that the object can fall to the yard side which is on the west side, instead of building side, if it is collapsed. 3. Installing method of piping piece Helicopter will be used for dropping down a piping piece to the top of the cylinder. |
| 63 | 97 | Silica glass Largr diameter fiber cable for high power laser delivery | A-1 | Fujikura Ltd. | Fujikura offers silica glass large diameter fiber (LDF) for high power laser delivery for cutting and welding process. This silica glass fiber has high durability for radiation, too. We have superior experiences of fiber coupling, connecting and optics technologies. This technology will provide a solution for laser cutting and drilling process. |
| 64 | 98 | Debris Removal System | B-1 | Westinghouse Electric Japan, Nuclear Fuel Industries | Removing Fuel Debris by using Fuel handling machine with manipulators. |
| 65 | 99 | Remote LIBS probe for in situ identification of fuel debris under water | A-2 | French Alternative Energies and Atomic Energy Commission (CEA) | The Laser-Induced Breakdown Spectroscopy (LIBS) technology is based on the use of a pulsed laser that is focused onto the sample surface, providing sufficient irradiance to generate ablation of the surface and create a plasma. Emission lines of the light emitted by the plasma can be recorded, and their analysis directly gives information on the elemental composition of the sample. The LIBS technique is fully based on optics, and gives the results within a few seconds. Consequently, it is particularly suitable for remote analysis. A specific LIBS probe could be conceived and integrated on automated robot for diagnostic under hostile conditions, and particularly for in situ detection of fuel debris under water. |
| 66 | 100 | (IRID reference translation) Concurrent implementation of multiple FEED | B-2 | プラント技術者の会 筒井哲郎 | (IRID reference translation) 1. Cause of the problem. For example, we already placed the order for the application of frozen ground wall but we are conducting small scale experiment for now. This means that we are just promoting development at present stage. Also, bidding requirements does not state the deadline for construction completion. To implement measures on handling of the accident, detail investigation and its corresponding measures are necessary in most cases. On the other hand, constructions are required to be completed at the earliest possible date. 2．Parallel implementation of multiple FEED In general, to start project including large scale technical issues that we deal for first time, Front End Engineering Package (FEED) for value will be ordered for several companies. Thus the risk of causing a deviation in the investment value after starting the construction because of vagueness of technology or large amount of investment can be minimized. This general rule should be applied to the selection of construction method of underground water shielding wall for the disposal measures on contaminated water. |
| 67 | 101 | (IRID reference translation) Air cooling for melted fuel debris | B-2 | プラント技術者の会 筒井哲郎 | (IRID reference translation) Heating value of melted fuel debris had already decreased to the level capable of being cooled down by air. Here I propose a plan and concept. Also I would like to ask for information on construction requirements for the current facilities and propose concrete design based on the requirements. Current heating values are as follows in reference to the actual result of heat removal by water cooling. Unit No.1 about 60kW Units No.2/ No.3 about 150kW In the Unit No.1, fuel debris is assumed that is solidified on the concrete surface at the bottom of the containment vessel. If those are cooled by air, debris surface temperature is about 300°C on the upper surface, about 150°C on the bottom surface at a rough estimate, and the maximum temperature in the debris is about 850°C. Debris inside the Unit No.2/ No.3 is assumed that is in the state of cylindrical lump and located on the top of the lower plenum. Therefore, upper and lower surface of temperature of debris is about 450°C and about 450°C respectively and the maximum temperature in the debris is about 1600°C. |
| 68 | 102 | (IRID reference translation) Shielding wall that substitute for frozen ground wall | B-2 | プラント技術者の会 筒井哲郎 | (IRID reference translation) Frozen ground wall may have possibility to be wasted in terms of technical reliability, workability, and cost. Problems are described below. 1) Actual freezing method was applied as temporary method. Also, the method used this time is one digit larger than actual result. 2) Water flows all over the site, and there are the layers of non-pressurized underground water and pressurized underground water. The behavior of underground water is extremely complicated. 3) Since underground water is pumped by deep well, water channel with fast flow velocity might be created. 4) Intensive controls and its corresponding measurements and control are required. The structure of a large group is necessary to maintain those over the entire length. 5) Building is located in the high dose area, and a large quantity of work should be done by the experienced workers. As an alternative plan, if the area a few hundred meters or 1 km away on the mountain side is insulated such as by the clay wall, diaphragm slurry wall, continuous concrete wall which are proven by existing technology the purpose will be achieved. |
| 69 | 103 | Simulation and costing for chosing best scenarios | B-1 | CEA (French Alternative Energies and Atomic Energy Commission) and OREKA Sud | Methods and techniques to help operators who have to choose for best scenarios depending on the parameters to optimize: integrated doses, outlets, wastes, man power hours, schedule, costs, etc.: 1. validate intervention scenarios, by simulating at scale one, 2.verify accessibility by virtual reality (immersive room), 3. show scenarios in a more user-friendly way, validate task ergonomics, 4.communication support ex: 3D views and scenes for communication with safety authorities, public, etc. , 5. help defining the needs, making bids, analysing quotes with respect to the data structure. |
| 70 | 104 | Simulation and costing for chosing best scenarios | A-1 | CEA (French Alternative Energies and Atomic Energy Commission) and OREKA Sud | Methods and techniques to help operators who have to choose for best scenarios depending on the parameters to optimize: integrated doses, outlets, wastes, man power hours, schedule, costs, etc.: 1. validate intervention scenarios, by simulating at scale one, 2.verify accessibility by virtual reality (immersive room), 3. show scenarios in a more user-friendly way, validate task ergonomics, 4.communication support ex: 3D views and scenes for communication with safety authorities, public, etc. , 5. help defining the needs, making bids, analysing quotes with respect to the data structure. |
| 71 | 105 | Area A2 - Crawler for removal of fuel debris | A-2 | NUKEM Technologies GmbH | Removal of fuel debris under water will require mobilisation of material sticking to surfaces, followed by some catching and transport. NUKEM has developed and successfully applied a crawler, a self-propelling underwater vehicle, equipped with handling equipment which is remotely controlled. such a crawler would be adapted to the F1 environment, and may be developed further as carrier for other detection and ermoval devices. |
| 72 | 106 | B2 - Crawler for removal and inspection of fuel debris | B-2 | NUKEM Technologies GmbH | Removal of fuel debris under water will require mobilisation of material sticking to surfaces, followed by some catching and transport. NUKEM has developed and successfully applied a crawler, a self-propelling underwater vehicle, equipped with high pressure water jets and sucking equipment, which is remotely controlled. such a crawler would be adapted to the F1 environment, and may be developed further as carrier for other detection and ermoval devices. |
| 73 | 107 | Conceptual study of fuel debris removal from the RPV and PCV of Units № 1-3 of Fukushima-1 | B-1 | Sosny Research and Development Company | General approach to development of a concept of the technology to remove fuel debris from PCV/RPV and work milestones are provided. Water submersion technique and alternative approach to fuel debris removal in atmospheric condition are compared. A concept of alternative technology for fuel debris removal in atmospheric condition through the PCV cavity using a module is proposed. This module represents a capsule with remote robotics equipment for fragmentation and collection of structural elements and fuel debris inside RPV/PCV. Reactor equipment and fuel debris are cut and removed by this module. It is suspended to the protective slab on the rail vehicle on the operating floor. Issues of air ventilation in PCV/RPV are considered. |
| 74 | 108 | (IRID reference translation) Fuel debris removal using forming of carbonated water and shock wave | B-1 | 高エネルギー加速器研究機構名誉教授 加藤和明、山本和浩 | (IRID reference translation) After filling containment vessel with carbonated water, fracture the fuel debris into tiny pieces by the shock wave generated by shock wave generation equipment that is equipped with focus point control function installed in the containment vessel. Since pieces of fractured fuel debris is floated by being in the gas bubble of carbonic acid generated by carbonated water, remove those by absorbing or scooping up. Both robot and human do not need to approach the fuel debris, and since operation is carried out in the state of being submerged, exposure dose can be minimized. Furthermore, unmanned continuous operation can be achieved and we can create negative pressure inside the nuclear reactor. Fuel debris at the bottom part of nuclear reactor which is a complicated structure by being damaged by the accident can be removed by being floated. Since the structure is simple, both facility fee and operation fee are low and additional radioactive contaminant to be caused during the removal operation can be minimized. Also, generated C13 is stable isotope. Since gas bubble grows fast because of heat generated by fuel debris, supersaturating state of carbonic acid gas can be controlled, and floating capability of carbonic acid gas is exclusively high compared to the air of existing technology. |
| 75 | 109 | Suppression Chamber | A-2 | National Nuclear Laboratory Ltd. | On clarification of site conditions NNL propose access to Torus via a diamond drilled access port from above chamber. A wall climbing/SC traversing vehicle will carry Ultrasonic Transducers (UT) and neutron backscatter probes; plus additional instrumentation i.e. camera, temperature, radiometric and will be lowered through access port onto S/C. A separate camera and / or laser scanner would be lowered through the access port to provide an operator view. The vehicle, neutron backscatter and UT detectors would be driven along the S/C surface until water level is detected. The UT and neutron backscatter probe provide independent methods of determining the water level within the S/C. Once water level detected, its location is confirmed by visual indication using the camera and laser scanner. |
| 76 | 110 | Investigation of the PCV Interior through available reactor penetrations X-53 & X-6 | A-2 | National Nuclear Laboratory Ltd. | X-53: Pan Tilt Zoom (PTZ) camera containing lighting deployed using NNL horizontal inspection system to survey and confirm if route X-6 is viable. X-6: A deployment system, delivering a PTZ camera, radiometric and temperature sensors to overhang the pedestal edge. It will provide a detailed view, radiometric and temperature data up to the RPV base and downwards to the PCV base in addition. |
| 77 | 111 | Investigation of the PCV Interior through Unit 1 X-100B | A-2 | National Nuclear Laboratory Ltd. | National Nuclear Laboratory (NNL) has experience in the deployment of remote controlled devices into highly active environments. NNL have experience of utilising and developing proprietary crawler devices in challenging nuclear environments for measurement and inspection tasks. The NNL intend to collaborate with a manufacturer of a proprietary system to miniaturise and develop an existing device that will deploy the NNL High radiometric detection device for high radiation measurements combined with an integral K type thermocouple. High quality Pan Tilt Zoom (PTZ) camera will be incorporated into the system. |
| 78 | 112 | MEDOC Hard decontamination process | B-2 | SCK•CEN (Belgian Nuclear research Center) | A hard chemical decontamination process called MEDOC was developed by SCK•CEN with a goal to maximize the clearance of materials. It consists in a single step treatment in a cerium acid solution, incl. Cerium 3 regeneration. Single step dissolution of both oxide layer and base metal is achieved, based on trans-passive oxidation and acidic dissolution. The MEDOC chemical decontamination process was firstly used in 1999, when applied to the dismantling of the BR3-PWR reactor in Mol (Belgium). Batch adapted treatments were used for stainless steel, carbon steel and aluminium. Closed loop treatment was selected for major components like the steam generator. The BR3 is the first PWR, designed by Westinghouse, to be put in operation outside USA, in 1962. |
| 79 | 113 | BellJar | B-2 | National Nuclear Laboratory Ltd. | NNL have developed and deployed two bell jars on Sellafield Site to assess activity released from disturbed sludge to the liquor phase. This has been used to assess/predict the downstream effluent treatment burden during future retrieval operations. This could potentially be deployed in SFP/RPV to assess the activity released to the liquor from any sludge deposits in SFP/RVP. The benefit of this would be an understanding of the expected effluent treatment requirements. |
| 80 | 114 | (IRID reference translation) Liquid shielding material that does not deteriorate under high dose rate condition | B-2 | Ryouichi Kubo | (IRID reference translation) We developed liquid shielding material that stably disperse heavy metal particle in the liquid. Normally dispersing agent will be added, but most of the dispersing agent is organic compound to disperse heavy metal particle in the liquid stably. If radiation is applied, it will be dissolved and capability of dispersing agent is impaired. As a result, particle cannot be dispersed and will precipitate. Therefore normal dispersing agent cannot be used for liquid that can maintain stable shielding capability under the irradiation. The liquid shielding material developed this time does not contain normal dispersing agent, and it can maintain stable shielding capability under the irradiation. Also, since its manufacturing method is relatively easy, we can make mass production. |
| 81 | 115 | Mega‐Gray Radiation Tolerant Integrated Circuits (MAGyICs) | A-2 | SCK•CEN (Belgian Nuclear research Center) | The MAGyICs research group of KU Leuven has developed with SCK-CEN integrated circuits (IC) that are able to operate until gamma radiation doses of 1 MGy and higher. This lead to a unique design methodology, that allows developing custom tailored MGy tolerant instrumentation solutions. Hereby MAGyICs reaches a radiation tolerance 1000 times larger than most commercial available electronics. |
| 82 | 116 | Torus Room Fuel Removal Strategy | B-2 | SimplyInfo.org Research Team | Visual and radiation evidence shows the high likelihood that fuel debris exists in the torus room of unit 1. An innovative approach independent of the work to retrieve fuel debris inside the PCV will be needed to address this issue before grouting of the torus room. By accessing these areas through the first floor and using a remote cutting and extraction tool as described, this work could be done readily and provide early fuel debris samples for analysis. The cutting head tool would be ideally suited for dislodging the pumice type debris found in the torus room. A pumping system with or without an auger would remove the debris from the underwater location directly to a shielded container for automated handling and replacement |
| 83 | 117 | VISIPLAN ALARA Planning Tool | A-2 | SCK•CEN (Belgian Nuclear research Center) | SCK•CEN has developed the 3-D VISIPLAN Alara planning tool allowing real radioprotection optimization by developing and comparing different scenarios and searching for the best option. Applying the code in a reverse way allows determining the radiation sources location and strength, based on discrete measurements of the radiation field. The main input of this project will be the delivery of the code, including the training of the dedicated personnel and the return of experience. This task will also comprise the setup of an interface allowing automatized data transfer from CAD data to the VISIPLAN input deck. |
| 84 | 118 | REX BR3-PWR Decommissioning (remote dismantling) | B-2 | SCK•CEN (Belgian Nuclear research Center) | The SCK•CEN has been the main contractor for the complete dismantling of its BR3 PWR plant. The project has been selected as pilot decommissioning project by the European Commission, and several technologies and processes have been tested and compared on a real facility and highly active components. This know-how can thus be very valuable in carrying out the fuel debris recovery and dismantling of the Fukushima Daiichi plants. The BR3 reactor in Mol (Belgium) is the first PWR to be put in operation outside USA, in 1962. This reactor had a power output of 40.9 MWth (10.5 MWe), the primary loop being composed of 1 steam generator and two primary pumps (so called 1.5 loop). It served as training centre for future NPP operators and as test bench for advanced PWR fuel (MOX). |
| 85 | 119 | Ultrasonic measurement of thickness and mechanical property of fuel debris fallen onto the pedestal | A-2 | Kazushi Yamanaka Ph.D., Professor, Department of Materials Processing, Tohoku University | It is needed to measure the (A) position and shape, and (B) thickness and mechanical properties of fuel debris fallen onto the pedestal, in order to retrieve the debris and to maintain the integrity of the pedestal. Optical measurement cannot measure (B) although it can measure (A). In contrast, ultrasonics can measure (A) and (B). However, the echo from the interface between the debris and concrete will be weak due to melting and adhesion of the debris to the concrete. In this case, nonlinear response of the debris will be useful to distinguish it from the concrete. In particular, subharmonics at the half frequency of the incident wave is advantageous due to its lower attenuation. The effect of irregular surface can be compensated by using the ultrasonically measured surface topography. |
| 86 | 120 | Conceptual Ideas and associated techniques for remote NDE under high dose rate | A-1 | ONET Technologies | ONET Technologies has a long experience and excellent track record in remote investigation, especially for Nuclear Reactor Pressure Vessels. This experience comes from more than 20 years of inspection services provided for the French reactors fleet. ONET has developed various investigation techniques, as televisual inspection, US, RT, Eddy Current with fit-for-purpose carriers and numerical modeling software. Based on this experience, ONET Technologies is able to adapt / develop specific equipments / material for a various range of investigations that will be needed in the Fukushima damaged RPV / PCV The information provided are a summary of capabilities and track records of remote investigation equipments and methodologies developed for specific applications in RPV under high dose rate |
| 87 | 121 | Advanced remotely operated system for dismantling, retrieval of high irradiated wastes | B-1 | ONET Technologies | With the largest engineering staff from a French private company dedicated to nuclear dismantling and waste management, ONET Technologies design and operate various equipments and technologies for major dismantling project, included waste retrieval systems (reactors, back end fuel facilities, laboratories,…). We are developing a full system, combination of innovative technologies that could be adapted to remove fuel debris from Top side in atmospheric condition, but also under water. Our solution includes: Advanced remotely operated system for dismantling & waste retrieval Waste treatment station |
| 88 | 122 | A safe aspiration system to retrieve the fuel debris. | B-1 | OAKRIDGE SAS | A pump and its connected flexible pipe specially designed would aspire the fuel debris, after cut. Calculations would be made in order to face safety challenges of the system such as criticitality, radiation shielding, pressure loss, material resistance.. |
| 89 | 123 | Corium “Cone” Fuel Debris Location Investigation | B-2 | SimplyInfo.org Research Team | This plan uses existing technical knowledge to target potential areas of fuel debris in containment, in the reactor building and outside of the reactor building. Drilling and probes used in the target areas of the “cone” will help confirm fuel debris location and condition with accuracy. |
| 90 | 124 | Internal PCV/RPV Investigation - Conceptual Study on Alternative Approaches | A-1 | Cavendish Nuclear Ltd | This response is based on our experiences of: reactor decommissioning; Magnox and AGR reactor core inspection and maintenance; and novel radiometric instrumentation and analysis. We will study methods of deploying commercially available CCTV cameras, fiberscopes and radiometric instruments to inspect internal structures and fuel locations by creating new penetrations in the RPV. Options for the deployment of instrumentation will be based on techniques that we have used in reactor decommissioning and inspection. In the identification, development and selection of all options, Cavendish Nuclear can utilise its front-end engineering capabilities and specialist resources that are experienced in the delivery of Concept and Option Studies for many Clients in the UK and overseas. |
| 91 | 125 | Fukushima Inspection and Remediation Manipulator (FIRM) | A-1 | MDA (MacDonald, Dettwiler and Associates Inc.) | A remotely controlled long reach robotic manipulator system could be used to investigate the interior of the PCV and RPV. These systems have been used successfully in the past in space and in Canadian nuclear reactors and at US DoE sites. MDA has recently developed one for CANDU reactor inspection that is very similar to that required for the PCV/RPV investigation. It could be modified to suit Fukushima’s specific requirements. Such a system would create the capability for reliable access to the PCV/RPV interior; repeated, safe, controlled access to this area is crucial for the success of the multi-year decommissioning project. Initial operations would focus on inspection tasks, but would evolve to include the deployment of tooling to assist in the removal of fuel debris. |
| 92 | 126 | Internal PCV/RPV Investigation - Technologies Required for Internal PCV/RPV investigation | A-2 | Cavendish Nuclear Ltd | This response is based on our experience of Magnox and AGR reactor core inspection and maintenance equipment; and novel radiometric instrumentation and analysis experience that includes radiometric instrument manufacture. We will identify equipment for internal PCV/RPV investigation including commercially available and proven CCTV cameras, fiberscopes and radiometric instruments to inspect internal structures and fuel locations. Our experience of the following technologies can be used in the visual or radiological inspection inside the RPV: CCTV cameras, borescopes, flexible fiberscopes, and gamma imaging devices. RadScan© based Gamma Imaging Tomography is proposed for the identification of fuel locations from measurements made outside of the PCV. |
| 93 | 127 | Fuel debris retrieval safety management | B-1 | Institute for Radiological Protection and Nuclear Safety (IRSN) | The risk of additional radioelements release and the risk of recriticality at the different stages of the fuel debris retrieval process are key issues. To manage these risks, it is necessary to have a precise description of the accident progression to identify the fuel debris location, their morphology and composition. According to the remaining uncertainties in the simulation of an accident progression, the risk management strategy has to be organized as an iterative process where the investigations in the containment and in the vessel and the successive collections and analyses of debris samples will allow adjusting the initial bounding evaluations. Accordingly, criticality calculation should be updated. A specific focus will be put on debris monitoring during removal operations. |
| 94 | 128 | Innovative approaches to fuel debris investigation and retrieval | A-1 | AMEC Nuclear International Limited | Extensive engineering development is required to ensure a solution for Fukushima. AMEC has encountered major challenges on nuclear plants where there is no immediate solution. By engaging experts from AMEC and the supply chain, innovative solutions have been developed and the problem resolved. AMEC uses its supply chain to provide specialist knowledge and equipment across the nuclear industry. Typically these companies specialise in: Gamma cameras/monitors, robotic systems, radiation tolerant viewing and detection systems. AMEC also has contacts with universities that perform research in the nuclear field, including: Muon Tomography, radiation detection and radiation hardened electronics. See file 1 for details of the supply chain. More information is available on request to AMEC. |
| 95 | 129 | Fuel-Debris Retrieval from PCV/RPV - Conceptual study on innovative approaches to fuel debris | B-1 | Cavendish Nuclear Ltd | Cavendish Nuclear’s conceptual study for dismantling reactors and fuel debris recovery will investigate options in support of potential use of an annular work platform lowered down into the RPV from above. Below the annular work platform, remote operated tooling will be deployed to cut and retrieve material from the RPV. A separate waste handling hoist will lift cut items. The suspended annular work platform approach is based on Cavendish Nuclear design for Dounreay Shaft waste recovery project that has to recover various wastes from a depth of 65m. In identification, development and selection of options, Cavendish Nuclear utilises its engineering capabilities and specialist resources experienced in the delivery of Concept and Option Studies for many Clients in UK and overseas. |
| 96 | 130 | Cask Insert and Service | B-1 | Mr. John Duryea, Westinghouse Electric Company | Developed loading procedures for cask systems and provided recommendations to resolve unique fuel storage challenges. |
| 97 | 131 | Fuel-Debris Retrieval from PCV/RPV - Technologies for Fuel-Debris Retrieval | B-2 | Cavendish Nuclear Ltd | Cavendish Nuclear's concept for reactor dismantling and fuel debris recovery is to use an annular work platform lowered down into the RPV from above. Below the annular work platform remote operated tooling will be deployed to cut and retrieve material from the RPV. A separate waste handling hoist will lift cut items. The suspended annular work platform approach is based on the Cavendish Nuclear design for the Dounreay Shaft waste recovery project that has to recover waste down to a depth of 65m. Technologies required for the innovative approaches include: • Removing fuel debris • Remotely operated deployment systems • Radiation shielding systems. • Equipment tolerant of dose rates anticipated • Systems for creation of new PCV and RPV penetrations • Fuel debris storage |
| 98 | 132 | Innovative approaches to fuel debris investigation and retrieval | B-1 | AMEC Nuclear International Limited | Extensive engineering development is required to ensure a solution for Fukushima. AMEC has encountered major challenges on nuclear plants where there is no immediate solution. By engaging experts from AMEC and the supply chain, innovative solutions have been developed and the problem resolved. AMEC uses its supply chain to provide specialist knowledge and equipment across the nuclear industry. Typically these companies specialise in: Gamma cameras/monitors, robotic systems, radiation tolerant viewing and detection systems. AMEC also has contacts with universities that perform research in the nuclear field, including: Muon Tomography, radiation detection and radiation hardened electronics. See file 1 for details of the supply chain. More information is available on request to AMEC. |
| 99 | 133 | Innovative approaches to fuel debris investigation and retrieval | A-2 | AMEC Nuclear International Limited | Extensive engineering development is required to ensure a solution for Fukushima. AMEC has encountered major challenges on nuclear plants where there is no immediate solution. By engaging experts from AMEC and the supply chain, innovative solutions have been developed and the problem resolved. AMEC uses its supply chain to provide specialist knowledge and equipment across the nuclear industry. Typically these companies specialise in: Gamma cameras/monitors, robotic systems, radiation tolerant viewing and detection systems. AMEC also has contacts with universities that perform research in the nuclear field, including: Muon Tomography, radiation detection and radiation hardened electronics. See file 1 for details of the supply chain. More information is available on request to AMEC. |
| 100 | 134 | Innovative approaches to fuel debris investigation and retrieval | B-2 | AMEC Nuclear International Limited | Extensive engineering development is required to ensure a solution for Fukushima. AMEC has encountered major challenges on nuclear plants where there is no immediate solution. By engaging experts from AMEC and the supply chain, innovative solutions have been developed and the problem resolved. AMEC uses its supply chain to provide specialist knowledge and equipment across the nuclear industry. Typically these companies specialise in: Gamma cameras/monitors, robotic systems, radiation tolerant viewing and detection systems. AMEC also has contacts with universities that perform research in the nuclear field, including: Muon Tomography, radiation detection and radiation hardened electronics. See file 1 for details of the supply chain. More information is available on request to AMEC. |
| 101 | 135 | Reliable and heavy capacity rad-resistant Maestro Arm for Inspection and retrieval of Fuel debris | B-2 | CEA (French Alternative Energies and Atomic Energy Commission) and Cybernétix | Maestro Maestro is a global remote handling solution, developed around 6 degrees of freedom . The arm, made of stainless steel and titanium provides an exceptional encumbrance/dexterity/payload ratio. It exists in 2 different lengths, depending on the operations. The operator can feel the effort applied on the arm through force feedback.Maestro can be operated, depending on operation’s requirements, with a master arm or Joysticks or pre-programmed movements. When operating with Master Arm, the hydraulic slave arm reproduces the movement the operator makes with the master arm. Maestro system is also composed with Hydraulic power unit (embedded or not), high rad resistant vision system, and various tools for inspection, cleaning, mechanical and thermal cutting. |
| 102 | 136 | An alternative idea to remove the nuclear fuel | B-1 | Soichi Terada | (IRID reference translation) Build a huge tunnel at the bottom of the reactor by shield method used for underground railway and road. Make a hole on the top of the tunnel and drop fuel as reactor core itself into the tunnel and then close the tunnel. (Seal in the debris by moving it to the vertical downward direction). |
| 103 | 137 | Lahoda Hot Cell | A-2 | Mr. John Duryea, Westinghouse Electric Company | Isolation “hot” cell for radio-chemical analysis capabilities supports analysis of various samples. |
| 104 | 138 | Candu Energy Inc.’s Proven Innovative Capability for Fuel Debris Retrieval at Fukushima Daiichi NPS | B-1 | Candu Energy Inc. | Candu has vast experience in successful remote spent fuel debris inspections, sampling and retrieval through innovative custom-designed methods. Candu has continually developed its remote reactor core inspection technology including equipment delivery, visual and NDE, debris handling and removal, etc. Specific challenges and obstacles with which Candu has experience that are similar to the current Fukushima Daichi situation are distance from operator to target area, air and underwater, very high radiation fields, uncertainty in target areas, remote operations, handling of highly radioactive material (including spent fuel), one delivery system for multiple capabilities: highly radiation tolerant camera, grappling devices, sampling devices, vacuum nozzles, NDE probes, drilling devices, etc. |
| 105 | 139 | Proven Neutronics Measurements Utilizing Solid State Track Records | A-2 | Mr. John Duryea, Westinghouse Electric Company | Solid State Track Recorders (SSTRs) are a mature neutron detection technology. |
| 106 | 140 | High Rad Camera & Delivery Technologies | A-1 | Mr. John Duryea | Westinghouse and its design teams will work to customize high radiation resistant inspection camera and delivery assemblies to a specified tolerance and design life specified by IRID. |
| 107 | 141 | METHODS AND TECHNIQUES TO IMPROVE MEASUREMENT AND RADIOLOGICAL CARTOGRAPHY | A-2 | CEA (French Alternative Energies and Atomic Energy Commission) | Different unmanned systems for detection of radiological activity (leaks, etc.) and rapid cartography restitution: • Non- destructive and distant measurement • GPS /WIFI reporting • Geostatistics to provide reliable methods for activity estimation, uncertainty quantification and risk analysis |
| 108 | 142 | Segmentation Cutting, Joining, and Sealing Technologies | A-1 | Mr. John Duryea | Westinghouse has developed several cutting, joining and sealing technologies used to segment and remove reactor internals in various light water reactor applications. |
| 109 | 143 | Fuel debris containers (FDCs) that support integrated recovery, transport & safe storage of debris | B-1 | NAC International Corporation, Norcross, Georgia, USA 30092 +1 770-447-1144 | This response addresses development of fuel debris containers (FDCs), transfer casks and other equipment and processes that can be used to collect and store recovered fuel debris safely. This includes criticality, radiation and hydrogen generations safety. NAC designs use the same hardware to collect the fuel debris, transfer it out of the reactor, to other pool storage, directly to onsite dry storage, and eventually offsite. Avoiding additional handling will improve safety. NAC is also proposing to refine processes for integrating fuel debris packaging; including eliminating moisture (and therefore any hydrogen generation) from fuel debris and damaged fuel stored in the FDCs. NAC will refine our Hot, Inert Gas Homeostatic Drying process to meet the specific needs for fuel debris drying. |
| 110 | 144 | Fuel debris containers (FDCs) that support integrated recovery, transport & safe storage of debris | B-2 | NAC International Corporation, Norcross, Georgia, USA 30092 | This response addresses development of fuel debris containers (FDCs), transfer casks and other equipment and processes that can be used to collect and store recovered fuel debris safely. This includes criticality, radiation and hydrogen generations safety. NAC designs use the same hardware to collect the fuel debris, transfer it out of the reactor, to other pool storage, directly to onsite dry storage, and eventually offsite. Avoiding additional handling will improve safety. NAC is also proposing to refine processes for integrating fuel debris packaging; including eliminating moisture (and therefore any hydrogen generation) from fuel debris and damaged fuel stored in the FDCs. NAC will refine our Hot, Inert Gas Homeostatic Drying process to meet the specific needs for fuel debris drying. |
| 111 | 145 | High-radiation Gamma and Neutron Imaging for Fuel Debris Location | A-2 | Createc Ltd | The proposed technology is a compact, high radiation imaging system for locating high-radiation items such as fuel debris. The technology is already established for medium dose rate gamma radiation; we propose further development of the system based on neutron and / or high gamma radiation sensors. Neutron gamma imaging has been demonstrated by Createc and Lancaster University in the laboratory and can be used to approximately locate fuel where heavy shielding is present. High dose gamma imaging is feasible in close proximity to fuel debris and can be used inside the PCV to precisely identify each item of debris. Both techniques exploit Createc’s unique compact radiation imaging technology to produce small remotely deployable radiation imaging device. |
| 112 | 146 | Mobile Tool Platform: Remote tool deployment system for reactor segmentation + fuel debris retrieval | B-2 | PaR Systems, Inc. | PaR proposes the Mobile Tool Platform (MTP), similar to equipment that PaR has built for Chernobyl NSC. The MTP is intended for stable deployment of inspection, cutting, sorting, and recovery tools at long reaches. The MTP is ideal for submerged or open air top down access for reactor internal segmentation and fuel recovery. The advantage of the MTP is its ability to deploy a stable platform at the extensions required to reach the 35 meters or more to the bottom of PCV. A telescopic mast is greatly disadvantaged when compared to the MTP in weight, safety, reliability and seismic stability; as it would most likely be beyond the bounding load of the deployment platform. The MTP offers operational flexibility to deploy a variety of tools safely and reliably. |
| 113 | 147 | Advanced Robotics, New Radiation Detection Sensors and Proven Rad-Tolerant Cameras & Electronics | A-2 | Mr. John Duryea, Westinghouse Electric Company | The proposed program includes the development, testing, deployment, and application of three remotely operated robotic platforms configured to perform energy dependent neutron and gamma radiation intensity measurements at desired locations inside the Primary Containment Vessels (PCV) at the Fukushima Daiichi Units that experienced significant core damage. |
| 114 | 148 | In-Situ Core Dissolution and Recovery | B-1 | Mr. John Duryea, Westinghouse Electric Company | Use the cooling water that is currently being recirculated over the now solidified molten fuel mass to move the fuel mass (U, fission products, other actinides) from inside the reactor vessel and the PCV to designated vessels on the outside of the reactor building. |
| 115 | 149 | PaR Systems Nondestructive inspection tools for fuel debris location and sizing. | A-1 | PaR Systems, Inc. | PaR proposes measuring the radiation from the fuel debris outside of the PCV/RPV to construct digital x-ray images using digital x-ray panel detectors. The results of the radiographs will be used to reconstruct the location and shape of fuel debris inside the PCV and RPV. The images will also be used to investigate the internal structure to prepare for fuel removal. This method will not require entry inside the PCV and will use the natural radiation of the material to construct radiographic images of the shapes and sizes of the internal structure. PaR also proposes measuring the water level inside a steel container using ultrasonic and backscatter x-ray technologies. The key is to use single-sided inspection technologies that are highly sensitive to the presence and absence of water. |
| 116 | 150 | Flowable Cementitious Composites for Containment Structure Repair and Fuel Debris Retrieval | B-2 | CTLGroup (Tim Tonyan, Senior Vice President) (Corporation) | The proposed approach uses a novel cementitious composite to plug leaks and cracks in the concrete of the containment structures and torus thereby enabling control of the appropriate water levels in the structures. CTLGroup has worked on the development of cementitious composites intended to be used to encapsulate nuclear waste sludge in nuclear facilities. The material had the unique ability to flow long distances without segregating, and incorporate the sludge as the grout flowed on, through and around the sludge.Testing of the composite demonstrated that the sludge was encapsulated in the grout. The cementitious composite was intended to be placed in a tremie type situation (underwater), via pumping. For plugging of leaks in Fukushima facility, we propose to use a similar technology. |
| 117 | 151 | AREVA - Conceptual study for internal PCV/RPV investigation. | A-1 | AREVA NC SA, International Projects | AREVA conceptual study will be based on accessing the inside of PCV/RPV through pipes or boring an access. The best way is to send investigation devices into PCV/RPV boring directly through the concrete wall and the PCV steel wall. This could be done: - from the 5th floor => enter the RPV and investigate the core, - from the 1st floor => investigate below the RPV (close to the melted core). |
| 118 | 152 | AARM :- Advance Airborne Radiation Monitoring | A-1 | Interface Analysis Centre, University of Bristol | The AARM system is the world’s first autonomous low altitude aerial radiation detection device. Using micro-computers to integrate lightweight gamma spectrometers with an unmanned aerial vehicle (UAV), the system allows the operator to accurately assess a radiological hazard at a remote and safe distance, providing real-time information on the isotopes composition, intensity and location of the radiation anomaly. The instrument securely transmits the location, identity and intensity of radionuclide contamination to a remote operator or base station. It can be operated manually, using traditional radio-controls, or semi autonomously via programmed GPS way-points. Utilizing simple interface software, these waypoints may be pre-selected or transmitted to the instrument in flight. |
| 119 | 153 | AREVA - Conceptual study for internal PCV/RPV investigation. | A-2 | AREVA NC SA, International Projects | AREVA investigation technologies, after accessing the inside of PCV/RPV using existing pipes or boring directly through the concrete wall and the PCV steel wall, will be based on existing and reliable solutions that will be fitted to the special Fukushima needs. As a exemple, investigation devices transported by a robot or a shielded shelter to carry people and equipments to the PCV concrete wall could be developed. |
| 120 | 154 | Diamond-based radiation detection systems for internal PCV/RPV investigation | A-2 | University of Bristol | We have developed an in-situ beta-gamma spectrometer that has been designed as a detector for mapping residual radiation in defuelled reactor cores. This device has been designed and manufactured over the last 12 months working in close collaboration with remote operations experts at Magnox Ltd in the UK. Our device has been designed with safety, redundancy and reliability in mind to reduce the potential of device failure. A key feature is that it has a radiation-hard sensors made from diamond (the only viable material for sensing in high-radiation environments). It is planned for deployment at Trawsfynydd in April 2014, to perform a complete mapping of the defuelled reactor core over a 2 week period. |
| 121 | 155 | AREVA - Conceptual study for fuel debris retrieval - B1 | B-1 | AREVA NC SA, International Projects | AREVA conceptual study will be based on our valuable experience due to its involvement in TMI PWR and Dounreay Fast Reactor fuel retrieval AREVA experience indicates that damaged fuel retrieval must be done from above using the existing biological protection during operations. Working under water will minimize the dose rate whereas, for atmospheric operations, retrieval canisters and casks will have to be designed to minimize the operators exposure. |
| 122 | 156 | AREVA - Conceptual study for fuel debris retrieva - B2 | B-2 | AREVA NC SA, International Projects | AREVA retrieval technologies, to be fitted to the special Fukushima needs, will be based on existing and reliable solutions. As an example, AREVA propose to work under water to minimize the dose rate. Whereas, for atmospheric operations, retrieval canisters and casks will have to be designed to minimize the operators exposure. AREVA has already a very valuable experience due to its involvement in TMI PWR and Dounreay Fast Reactor fuel retrieval. |
| 123 | 157 | Long Reach Manipulator Practical Uses for Internal PCV/RPV Investigation | A-1 | Vista Engineering Technologies, Inc. | The VET-RSS Division specializes in the design, fabrication, and testing of remote systems to deploy a variety of tools to inspect, clean and remove hazardous materials within nuclear environments including the Fukushima Daiichi Nuclear Power Station. Over the past 20 years RSS personnel have produced over 170 remote systems and tools. Our standout qualifiers are: Proven manipulator technology for a variety of remote retrieval applications; Expertise in lightweight, long reach, high payload, high-radiation carbon fiber manipulator systems; Proven ability to fit through existing penetrations; Proven track record of remote material handling; Able to deploy a variety of custom tools/end effectors for various remote operations; Small footprint to accommodate plant room dimensions. |
| 124 | 158 | Long Reach Manipulator for the Purpose of Fuel Debris Removal | B-1 | Vista Engineering Technologies, Inc. | The VET-RSS Division specializes in the design, fabrication, and testing of remote systems to deploy a variety of tools to inspect, clean and remove hazardous materials within nuclear environments including the Fukushima Daiichi Nuclear Power Station. Over the past 20 years RSS personnel have produced over 170 remote systems and tools. Our standout qualifiers are: Proven manipulator technology for a variety of remote retrieval applications; Expertise in lightweight, long reach, high payload, high-radiation carbon fiber manipulator systems; Proven ability to fit through existing penetrations; Proven track record of remote material handling; Able to deploy a variety of custom tools/end effectors for various remote operations; Small footprint to accommodate plant room dimensions. |
| 125 | 159 | Remote inspection of the core using cosmic ray tomography | A-2 | Jaap Velthuis, Bristol-Oxford NRC/University of Bristol | Bristol University has successfully developed large scale High resolution Resistive Plate Chambers (HRPCs) for Cosmic Ray Tomography (CRT). CRT is a technique that allows precise, remote imaging of structures like the Fukushima reactor cores. We propose to build a CRT system based on HRPCs to obtain precise information remotely about the location and nature of fissile material and debris inside the reactor pressure vessels. The concept behind CRT is that muons are measured before entering and after leaving the reactor cores. During interactions with matter, they will change direction through multiple scattering. The scattering depends on the material traversed. Studying many muons (the rate is roughly 100Hz per m2) gives information on the contents and structure of the reactor core. |
| 126 | 160 | Characterization and Inspection of Damaged Containment Vessels using Water-Borne Sensor Technology | A-2 | Southwest Research Institute (SwRI) | SwRI has developed a water-borne sensor (WBS) technology capable of collecting images of caves, boreholes, and culverts. Current WBS technology consists of a self-contained sensor platform that uses advanced data processing techniques to produce 3-D maps of cavities using ultrasonic sensors. SwRI staff is presently working to design and develop a next generation WBS system with propulsion and navigation capabilities. The sensor payload will also be expanded with additional sensors (cameras, dosimeters, temperature probes) to enhance the utility of the system. The next generation WBS system is expected to be capable of collecting data to characterize and inspect damage within the interior of containment vessels at Fukushima Daiichi. |
| 127 | 161 | Chemical Removal of Spent Fuel Debris | B-1 | Southwest Research Institute (SwRI) | Using a mild acid solution, for example dilute nitric or phosphoric acid, the spent fuel debris can be dissolved and pumped out of the PCV/RPV. The fission products and uranium fuel are oxidized metals. Dilute acid solutions, like phosphoric acid, are proven effective for rust (metal oxide) removal from metals. Using a dilute acid solution to dissolve and remove the spent fuel debris could allow the PCV to be emptied and placed under negative pressure, thus preventing more leakage into the surrounding soil. This could be done by pumping out the PCV, while the dilute acid solution is used to both cool the spent fuel and to dissolve radioactive metal oxides. Set up of the mild acid delivery and pumping system could be done while the PCV is still filled with water, for radiation shielding. |
| 128 | 162 | Melting and crashing removal technologies using laser lights for fuel debris and in-vessel structure | B-2 | Toshiharu MURAMATSU, Applied Laser Technology Institute, Tsuruga H/Q, Japan Atomic Energy Agency | (IRID reference translation) JAEA utilizes the shape cognitive function by laser distance meter for removal object, cognitive function for the temperature near the laser irradiation position by two-color thermometer, material cognitive function by spectrometer for removal object material as an external sensor, and promotes development and verification of the system focusing on the function that synchronously controls the robot control system, laser beam control system, and assist gas jet flow control system based on this information in order to apply to the fusing, fracturing technology using laser beam appropriately for removal of fuel debris characterized such as in indeterminate shape, high degree of hardness, multicomponent, porous. This system is equipped with control algorithm as an applicable control system to maintain the appropriate stats of laser beam fusion-cutting and fracturing performance (in the air and underwater) corresponding to the optional requirements of removal object Furthermore, we are promoting development and verification of calculation code to quantitatively verify laser beam irradiation requirement at the site of fuel debris removal. |
| 129 | 163 | Development of Alternative Approach to Support Fuel Debris Removal | B-2 | James M. O'Connell | Continued RPV leakage outside primary and secondary containment continues to complicate recovery of the site and a lack of water tight integrity substantially impairs any ability to remove the damaged core and its fragments. Given significant experience in the US with cementitious fill/grout to immobilize and to preclude contamination spread to the environment, the researchers believe that a fill/ grout based approach for sealing of the primary and secondary containments can help isolate the damaged cores from leaking to the environment as well as providing a means to flood up the primary containments and conduct defueling operations. |
| 130 | 164 | (IRID reference translation) New proposal of uel debris removal for Fukushima Daiichi NPS | B-1 | 貞包 健一郎(さだかね けんいちろう) | (IRID reference translation) i) Remove bottom part of containment vessel and reactor building concrete foundation, and ii) Drilling a steel sheet at the bottom part of containment vessel such as by plasma fusion, and iii) Collect those in the cask container, This is a method of removing fuel debris according to the procedures. Features: If large removal space can be secured for concrete foundation, operationability workability will be improved and it reduces radiation exposure dose. |
| 131 | 165 | Internal Cavity Probe to View and Characterize Debris | A-1 | Southwest Research Institute (SwRI) | Medical probes used in heart catheterizations and colonoscopies can maneuver very tight and complex passages with relative ease. SwRI can develop a flexible probe 2 to 5 cm in diameter to probe the insides of the PCV. The end of the probe can be mounted with radiation-hardened articulating cameras and lights, for 3D viewing of the debris, and a collimated radiation detector to map dose rates. Internal guide wires can move the tip of the probe to direct it around equipment and to scan the debris. The probe can also be equipped with directional water nozzles to help guide the probe in various directions during its placement and removal. The probe can be covered in a strippable outer covering, to allow for decontamination for relocation, repair or maintenance. |
| 132 | 166 | Electroplating Spent Fuel from Contaminated Water | B-1 | Southwest Research Institute (SwRI) | Using a sacrificial anode, the radioactive metal ions (fuel and fission products) can be electroplated onto a disposable metal plate or directly onto the inside surface of a shielded-steel tank, designed for solid waste disposal. This technique can also be used for cleanup of existing water tanks of stored contaminated/radioactive water. This technique will also remove hazardous and heavy metals found in the water, like cadmium (Cd) and lead (Pb). |
| 133 | 167 | (IRID reference translation) Radiation-resistant metal cable | A-2 | Fujikura Ltd. | (IRID reference translation) This is a product that was developed in collaboration with KEK and JAEA for study of long life cable used in the nuclear-related facility. We developed cable that Non-halogen flame retardant sheath can resist up to 2.5Mgy, comparing to 0.5Mgy. It may be used as a cable for transmission. Since this system can reduce frequency of replacement, fees for cable and construction can be deleted. |
| 134 | 168 | (IRID reference translation) Fuel debris removal system that combines telescopic tube with arm and plasma cutting | B-2 | Fuji Electric Co.,Ltd. | (IRID reference translation) The system I propose consists of telescopic tube with two arms, disassembled pieces storage basket, transportation crane for disassembled piece, transportation conveyer, crane for transportation used in the pool. Access inside the PCV/RPV can be achieved by telescopic tube that has two arms on its end. Out of two arms, one is the arm for holding and cutting disassembled pieces, the other one is for maintaining its position. Plasma cutoff tool which has relatively small reaction force is used for cutoff. There are two type of plasma cutting, which are arc type and jet type, but if we are ready for both methods, we can cut debris regardless of its conductivity. After cutting off, put disassembled pieces into basketball, and pull up to the upper portion of the containment vessel by using dismantling transportation crane for disassembled pieces. Then, transport those to the fuel storage pool by transportation conveyer and store them in the transport vessel. |
| 135 | 169 | LookUp Acoustic Debris-Imaging; Acoustic Probing of Debris buried in the concrete from Underground | A-1 | Nihon Chikatansa Co., Ltd. | Visualization of the debris from underground which fell on or was buried in the mat concrete. It consists of the following techniques. 1) Horizontal drilling for safety and smooth access to underground of R/B; also an effective method for time-lapse monitoring of debris-retrieval by any sensors. 2) Generation of acoustic wave outward from the borehole and receiving scattered waves from the debris; Combination of PRBS source, in which a partner JFE Civil holds the patents, and high-freq. sensors is suitable. 3) Visualization of the debris by using the first and the higher-order scattered waves; Advanced seismic imaging techniques, such as the viscoelastic full-wave inversion, developed by another partner GIM-labs, can be applied to localize and delineate the debris. |
| 136 | 170 | (IRID reference translation) WBLCX wireless LAN system | A-2 | Fujikura Ltd. | (IRID reference translation) WBLCX® wireless LAN system is capable of configuring optimum electric wave environment without wave dead zone by wiring WBLCX freely using cable type antenna (WBLCX®) as an antenna at access point. |
| 137 | 171 | Fuel Debris Retrieval Method Using Expandable and Rotational Platform Manipulator Machine | B-1 | Radwaste and Decommissioning Center, Japan Clean Environment Promotion Organization | The fuel debris retrieval Machine consists of a set of remote-controlled manipulators installed on 3 stages expandable & rotational platform and a crane. In the retrieval work in the air, a hole through PCV and reactor vessel is made, and steel cubes or balls are filled in the vessel to shield radiation from the debris. Then, the set of manipulators on the platform is inserted into the vessel to the pedestal floor. The debris and steel cubes are retrieved by the manipulators. In case of the retrieval work in the water, underwater manipulators are used to retrieve the debris. Extracted debris is put in containers and transferred to the spent fuel storage pool. |
| 138 | 172 | (IRID reference translation) Abrasive water jet cutting technology and monitoring technology applied for fuel debris and reactor internals | B-2 | 独立行政法人日本原子力研究開発機構 敦賀本部 原子炉廃止措置研究開発センター | (IRID reference translation) I propose the monitoring technology other than visual observation and removal technology using Abrasive Water Jet (AWJ) . Also, this technology can be applied underwater. (1) Monitoring technology other than visual observation If it is difficult to monitor the cutting condition by a camera because of high dose in the vessel of 1F, this will provide the technology that can estimate the cutting condition in real time by acoustics and frequency of vibration and difference in intensity generated when cutting an object. (2) Cutting method which is not affected by plate thickness Now, condition inside the reactor of 1F is not confirmed yet, in terms of fuel debris removal, the fuel and partial reactor internals are in indeterminate form due to melting and resolidification, and thermal and mechanical physical properties can be estimated to vary in each portion. Therefore I provide the cutting method which is not affected by environment where heating cannot be done, and plate thickness by using AWJ, which is the mechanical cutting capable of cutting various material with different physical properties. |
| 139 | 173 | (IRID reference translation) Plasma cutting technology for debris removal | B-2 | 日本原子力研究開発機構 大洗研究開発センター | (IRID reference translation) We are developing the plasma cutting technology (plasma arc and plasma jet) as a technology of removing such as of debris. Plasma arc has cutting capacity of steel plate thickness of 220mm or more in the air and plate thickness of 100mm or more under the water. Now we are conducting optimization test for cutting requirement to improve cutting capacity. Plasma jet is a technology to discharge between ends of electrode in the torch and cut objects by turning the gas into plasma and melting it. It is capable of cutting off the steel material of 50mm and firebrick by power output of 250A in the air and fracturing the firebrick of 150mm. Now, we are developing a torch that can be used underwater for power output of 600A as a cutting and fracturing technology used for removal such as of debris. These two technologies of cutting identified the impact caused by each type of parameter through the various performance tests and are able to provide optimum cutting requirements to remove such as debris. |
| 140 | 174 | Test Beds to Reduce Risk and Accelerate Workflow For Debris Characterization and Waste Removal | A-2 | Southwest Research Institute (SwRI) | The objective of the proposed project is to reduce risk and improve performance of robotic systems in advance of their deployment at the Fukushima reactor site. This objective will be achieved by developing a series of surrogate environments and test facilities for conducting risk-reduction experiments on proposed technologies prior to their deployment inside of the Fukushima reactors. This clean surrogate test bed would eliminate the unnecessary contamination of research prototypes and will also allow for the evaluation and consideration of otherwise unproven or high-risk approaches conducted under other research projects. |
| 141 | 175 | Approach inside PCV via Vent Pipes through VBL using snake-arm | A-1 | BCSN | Managing alternative approach inside PCV via Vent Pipes . Accesses can be as large as O380mm. Through these multiple access, underwater inspection devices can reach bottom of PCV, under the PCV grating and around pedestal in where melted core is contained, then reach inside it for debris inspection : Insert a remote “Snake arm” manipulator inside the vacuum break pipe up to lead into the Vent pipe (2x90° angle bends). Direct the “Snake arm” towards the bottom of vent pipe. Insert a deflated plug inside “Snake arm” hose, inflate the balloon & secure it by injection of expansive rigid PU foam (EasyPart). Leave and forget in place. |
| 142 | 176 | (IRID reference translation) Method to obtain lighing and electric power under high radiation environment.(Idea) | A-1 | 徳島大学 久田旭彦、徳島大学 伏見賢一 | (IRID reference translation) It is difficult to lay down a power cable since high radiation environment needs to be isolated from outside. Also, since it is indoor and dark place, we cannot use solar cell. Securing power source to operate lighting and equipment is assumed to be the issue. Therefore, I propose to obtain lighting and power from the radioactive substance, which is the cause of contamination. Scintillators will be used for lighting. Radiation on the site, being transformed into visible light, can be used as lighting. Zinc sulfide can be considered as an example. (This may be substituted such as by fluorescent paint.) This method can be expected to have an effect to visualize the radiation dose. Since it shines at the spot of high radiation level, we can keep a distance from there and it will be useful for reducing exposure. There is a possibility of solar power generation of radiation can be changed into the light of appropriate wavelength by using this method. Also, in the similar concept, power for equipment may be obtained from the radiation and heat released from fuel debris. |
| 143 | 177 | adaptation of existing hatches to be converted into “submarine” type airlocks | A-1 | BCSN | Managing alternative approach inside PCV, with adaptation of existing hatches to be converted into “submarine” type airlocks resisting to 5Mpas pressure (Flooded PCV) and with adequate shielding. It seems quite possible to convert Staff entrance and Equipment hatches into sealed & shielded airlocks for direct access on grating level floor inside Drywell wall of PCV. For the same, conversion of the South West Equipment hatch can also be envisioned. Of course, access dimensions will be reduced from original, but remaining large enough for Inspection & dismantling purposes. |
| 144 | 178 | Reconstructing Fuel Debris Locations Inside the PCV From Gamma-Ray Measurements Outside of the PCV | A-1 | Southwest Research Institute (SwRI) | Southwest Research Institute has relevant technology to assist with the fuel debris characterization. In the SwRI approach, fuel debris locations inside the flooded PCV are reconstructed from measurements of 3 dimensional changes in the gamma ray radiation field as a function of position outside the PCV. Due to gamma-ray attenuation by water in the PCV, fuel debris locations near the PCV walls can be determined from measurements outside the PCV. The technology can be applied to fuel debris characterization in a measurement system constructed from a commercially available gamma ray detector and integrated sensors for position and orientation of the detector relative to the PCV. SwRI contributions to the selection and fabrication of the measurement system are optional. |
| 145 | 179 | converting post-accidental useless mechanical & electrical penetrations into “submarine” type airloc | A-1 | BCSN | Managing alternative/complementary approach inside PCV by converting post-accidental useless mechanical & electrical penetrations into “submarine” type airlocks resisting to flooded PCV water pressure and with adequate shielding cabinet for safe operation in RB. For the same it can be envisioned to access inside RPV by converting piping connected to it, adding a shielded airlock on the line where location is the most adequate inside RB (replacing a valve or a pump for example). The advantage of existing piping with inner Ø>20mm is to offer enough space and accurate guiding line for introducing probes & tool heads in well known locations. Therefore it makes it easier for the study of remote adequate/specific tooling. |
| 146 | 180 | Remotely visual survey, inspection & measurement: | A-2 | BCSN | Remotely visual survey, inspection & measurement: Different topics are under development all through Bouygues group divisions. Some of these various R&D and studies can be adapted to our scope of work, e.g.: Ultrasonic camera (US scan): allows visual recognition in unclear or even dark water. This concept is actually under development in Bouygues Group, for tunneling applications. The main advantages are it’s almost insensitiveness to radiations compare to CCTVs, and of course no need for lightings, allowing miniaturization and easy adaptation for remote ops. Hardened CCTV cameras and electronics specially designed for working in hostile environmental conditions (underwater up to 60m deep, highly irradiated ambiance up to 300Gy/h, T°C up to 60°C). |
| 147 | 181 | Underwater Laser cutting and HP water jetting cutting: | A-2 | BCSN | Underwater Laser cutting and HP water jetting cutting: Bouygues Group development undergoing for using underwater cutting techniques, applied to the improvement of our Tunneling technology. These techniques shall be very useful for remotely dismantling inside PCV & RPV. |
| 148 | 182 | Laser scan | A-2 | BCSN | Laser scan: allows visual “as built” recognition in air. This process can be very useful for PCV survey inside the expected post accidental ruins inside pedestal. This technique has been already adapted by BCSN to carry on a fully remote “as built” survey under the graphite block of UNGG reactor SLA3. |
| 149 | 183 | (IRID reference translation) ”Melted fuel removal from freezing reactor ” | B-1 | shinbori hideomi | (IRID reference translation) To stop the cooling water leak from nuclear reactor is essential for countermeasures on contaminated water/operation of melted fuel removal from submergence. If we can freeze nuclear reactor, damaged portion will be freezed, and cooling water leak can be stopped and submergence can be done. 1. Method for freezing a nuclear reactor ･Construct huge freezing storage room to cover Unit No.1-3 reactor building and reduce lower the temperature inside the reactor building to freezing point. ･Cool down the cooling water to the freezing point. 2．Procedures for melted fuel removal According to normal operation, remove damaged fuel rod by the remote control crane from outside the building. Then, dismantle･remove the pressure vessel. After that, investigate and remove melted fuel at the bottom part of containment vessel. 3．Method of removing melted fuel If the melted fuel is in the form of particle, absorb it together with water by using a pump to remove. If it is fused on containment vessel, drain water, cut off the bottom part of containment vessel with applying cold air to the debris and hoist the debris by crane and remove it. |
| 150 | 184 | Remote operations using a “Snake Arm” system (OCRobotics): | A-2 | BCSN | Remote operations using a “Snake Arm” system (OCRobotics): Bouygues Group is adapting an OCRobotics “Snake arm” to investigate inside the 3-5Mpas hyperbaric front space of a tunneling, and especially for the survey of the wear of the cutting wheels. |
| 151 | 185 | (IRID reference translation) Debris removal from Pressure vessel (reactor)･contaiment vessel in dry state | B-2 | Individual(no affiliation) | (IRID reference translation) (1) Keep the inside of the vessel /containment vessel dried. (Protect flooded portion if there is any) (2) Install operation opening on the side of the containment vessel. (3) Retrieve the spent fuel from the top of the reactor. (4) From the opening on the side of containment vessel, open the bottom part of the reactor by radioactivity resistant boring robot using arc cutting machine, laser cutting machine, high pressure air cutting machine etc. (5) Cut and crush reactor component, debris etc. fallen in the bottom part of the reactor finely enough to be removed by radioactivity resistant crushing robot. (6) Cut and crush debris at the bottom of the containment vessel finely enough to be easily removed by radioactivity resistant crushing robot. (7)Retrieve the reactor component/crushed debris etc. which were cut down. After completion of removal, seal the openings. (8) In general, the intensity of radioactivity of radioactivated steel material/member etc. is considered to be reduced to one thousandth in 50 years. Pressure vessel (reactor) and containment vessel will be dismantled over the years. |
| 152 | 186 | Creation of these new accesses | B-1 | BCSN | Accessing to fuel debris from lateral side of PCV/RPV in atmospheric conditions, by converting post-accidental useless mechanical & electrical penetrations as per A-1.3 and A-1.2. Creation of these new accesses can allow proceeding for mechanical debris retrieval with robotic arms, and also installing automatic endless stream for shielded cans exit inside a shielded treatment facility built inside RB (ref. A.1.2): |
| 153 | 187 | a high density SolidPart HD mortar or a high density RTV resin | B-2 | BCSN | Shielding radiation emitted by high-dose fuel debris fallen inside pedestal: pouring a high density SolidPart HD mortar or a high density RTV resin overloaded with boric acid under the PCV grating around the Pedestal, after having installing a reservation room to preserve its bottom penetration to install a mechanical elevator for further operations of debris retrieval. |
| 154 | 188 | Image and Laser delivery composit optical fiber system for radiation environment | A-1 | Fujikura Ltd. | Fujikura developed unique optical fiber system which can deliver both image and high power laser light by using single composit optical fiber. This system developed for ITER cooling pipe maintenance with JAEA 20 years ago. It can offer visual onservation and laser processing at a time. This technology will help high power laser processing for drilling and cutting through thin pipe under radiation environment. |
| 155 | 189 | Technology to wrap up debris of any kind with our family of RTV resins | B-2 | BCSN | Technology to wrap up debris of any kind with our family of RTV resins (high density for gamma reduction, plain or overload with boric acid for neutron absorption, contamination fixing or removal, rusty protection …) in air or underwater. |
| 156 | 190 | (IRID reference translation) Computer tomography(CT)method for reactor using Gamma-ray | A-1 | Honorary professor of KEK, the High Energy Accelerator Research Organization, Kazuaki Kato Kazuhiro Yamamoto | (IRID reference translation) Only the effect is described. Method will be described in “Non-disclosure information.” If this technology is used, shape of the nuclear fuel debris, frame, and rubbles inside the nuclear reactor can be detected by Computerized Tomography (CT) using Gamma-ray. Maximum resolution is 5-10mm and CT image of overall nuclear reactor can be obtained by 3-dimensional measurement. Capable of distinguishing the nuclear fuel debris, iron, concrete, and plastic. Very low facility cost, and operation cost. Operation can be carried out with submerged condition and we do not need to be close to the nuclear fuel debris and the exposure dose can be minimized. |
| 157 | 191 | Boring, Cutting and Decontamination Method by NitroJet® for Internal PCV/RPV Investigation | A-2 | IHI Corporation | IHI proposes remote-controlled NitroJet® to bore and cut any concrete and metal which block access route, and to decontaminate dismantled internal equipment for internal PCV/RPV investigation. NitroJet® is the technology which decontaminates surface or cuts pipings/metal plates by an ultra-high pressure liquid nitrogen jet, so it does not generate any secondary liquid waste, and any secondary contamination can be prevented. NitroJet® can be applied to boring and cutting any shielding and metal using remote-controlled robot. NitroJet® can also cut metal plate as thick as 50mm with abrasive, therefore it can cut reinforced bars in shielding concrete at the same time. It is also helpful to decontaminate dismantled internal equipment in PCV/RPV. More detail is described in attachment1. |
| 158 | 192 | Optical fiber high precision water level and temperature gauge | A-2 | Fujikura Ltd. | High precision optical water level and temperature gauge by using silica glass fibers. This water level gause is used extensively at the water and sewage treatment plants and dams. It also equipped optical temperature gause which correct for the influence of water temperature to provide high accurate water level. |
| 159 | 193 | Remotely operated decontamination process | B-2 | BCSN | Remotely operated decontamination process using spayed RTV FA878 pelable coating on board of an automotive platform |
| 160 | 194 | Boring, Cutting and Decontamination Method by NitroJet® for Fuel-Debris Retrieval | B-2 | IHI Corporation | IHI proposes remote-controlled NitroJet® to bore and cut any concrete and metal which block access route, and to decontaminate dismantled internal equipment for ｆuel-ｄebris retrieval. NitroJet® is the technology which decontaminates surface or cuts pipings/metal plates by an ultra-high pressure liquid nitrogen jet, so it does not generate any secondary liquid waste, and any secondary contamination can be prevented. NitroJet® can be applied to boring and cutting any shielding and metal using remote-controlled robot. NitroJet® can also cut metal plate as thick as 50mm with abrasive, therefore it can cut reinforced bars in shielding concrete at the same time. It is also helpful to decontaminate dismantled internal equipment in PCV/RPV. More detail is described in attachment1. |
| 161 | 195 | (MHC Inspection Robot) | A-2 | Cybernetix | (IRID reference translation) Remote control robot that can inspect and investigate such as hull by using permanent magnet. Please refer to the attached files. |
| 162 | 196 | Acoustic Emission Sensor | A-2 | Cybernetix | (IRID reference translation) Crack and leakage point can be detected by the sensor using acoustics. Please see the attached file. |
| 163 | 197 | Boring, Cutting and Decontamination Method by NitroJet® for Internal PCV/RPV Investigation | A-2 | IHI Corporation | IHI proposes remote-controlled NitroJet® to bore and cut any concrete and metal which block access route, and to decontaminate dismantled internal equipment for internal PCV/RPV investigation. NitroJet® is the technology which decontaminates surface or cuts pipings/metal plates by an ultra-high pressure liquid nitrogen jet, so it does not generate any secondary liquid waste, and any secondary contamination can be prevented. NitroJet® can be applied to boring and cutting any shielding and metal using remote-controlled robot. NitroJet® can also cut metal plate as thick as 50mm with abrasive, therefore it can cut reinforced bars in shielding concrete at the same time. It is also helpful to decontaminate dismantled internal equipment in PCV/RPV. More detail is described in attachment1. |
| 164 | 198 | MAESTRO manipulator arm | B-2 | Cybernetix | (IRID reference translation) High radiation-resistant hydraulic manipulator with manual dexterity. -Applicable for using under water (in the air). -Equipped with force feedback function -Overwhelming experiences in decommissioning such as in France - Performance record in Japan. (Hitachi/TEPCO Manipulator for repairing shroud.) Please see the attached file. |
| 165 | 199 | Remote Laser Cutting System | A-2 | IHI Corporation | ・Remote laser cutting system ・Fiber length: 100m at maximum ・For metal cutting (SUS, steel, etc.) |
| 166 | 200 | (IRID reference translation) Dry type removal method for fuel debris without flooding a contaiment vessel | B-1 | 株式会社IHI | (IRID reference translation) Method to collect fuel debris of the nuclear power plant that caused an accident by dry method using remote equipment. Current plan of fuel debris removal method that submerges PCV has issues as follows; (1) It takes time to investigate and repair many openings that constitutes the PCV boundary. (2) Accessibility is poor because fuel debris are melted through and fallen in the PV pedestal which is located far from the floor surface of fuel replacement (Fifth floor of reactor building). Therefore, this information is to propose the removal method without submerging PCV. In this method, additional new openings can be installed on the PCV side since PCV is not submerged, and it can combine the two pieces of equipment that removes from the top of the fuel replacement floor and that removes fuel debris fallen in the RPV pedestal from the side of the PCV(First floor of the reactor building). Since this can remove fuel debris from two directions and shorten the distance for accessing to the fuel debris, efficiency can be expected to be improved. Material 1. |
| 167 | 201 | High radiation resistant optical fiber for data transmission for controlling drive system | B-2 | Fujikura Ltd. | Fujikura is the world leading company in the field of telecommunication fiber and cable. We also provide No.1 radiation resistant optical fiber to the accelerators at KEK, J-PARC and CERN. This RR-SM fiber demonstrates under 7dB/km under 100kGy radiation condition. |
| 168 | 202 | Remote Laser Cutting System | B-2 | IHI Corporation | ・Remote laser cutting system ・Fiber length: 100m at maximum ・For metal cutting (SUS, steel, etc.) |
| 169 | 203 | (IRID reference translation) Development of deveice to survey for contamination on the surface of storage can required for transporting fuel ebris | B-1 | ①富士電機株式会社 ②富士古河Ｅ＆Ｃ株式会社 | (IRID reference translation) Before starting full-scale fuel debris removal, sample of debris needs to be transported to the research facility located in the site to identify its properties. The sample of debris will be transported by being stored in the storage cans. In this case, level of radiation dose of debris can be easily expected to be extremely high, and contamination inspection in the storage cans will be performed at the exclusively high radiation level, and remote control apparatus to investigate the surface of storage cans will be required. This is to provide the information regarding equipment development. As shown in the support document 1 this is the equipment that combines the technologies of object shape detection and radiation detection, and robot arm function. Also, this will be the essential item for technology development to correspond with the full scale transportation of debris. |
| 170 | 204 | Acoustic Imaging System for Remote Controlled Equipment | A-2 | IHI Corporation | ・Acoustic Imaging system which is mounted on remote controlled equipment like a powered manipulator can provide additional visual information during remote operation. It should be very useful method for the remote operation, especially under the area where visuality is limited, such as turbid water. ・The system can also provide the distance information between the end-effector and the objects by noncontact. And as a result, it makes possible to improve the efficiency of noncontact-cutting and decontamination work (e.g. using laser and water jet system). |
| 171 | 205 | (IRID reference translation) Underwater laser cutting method | A-2 | IHI Corporation | (IRID reference translation) Since operation of internal PCV/RPV investigation is carried out in a high dose environment, interfacing equipment such as PCV, RPV, piping etc. are cutoff and dismantled by using remote control equipment, and secure the access route into the PCV/RPV. Underwater laser cutting is characterized by “Small cutting reaction force” and ”Cutting steel material in the air /underwater,” and this cutting technology is effective for remote dismantling under the high dose environment and environment underwater/in the air. |
| 172 | 206 | Acoustic Imaging System for Remote Controlled Equipment | B-2 | IHI Corporation | ・Acoustic Imaging system which is mounted on remote controlled equipment like a powered manipulator can provide additional visual information during remote operation. It should be very useful method for the remote operation, especially under the area where visuality is limited, such as turbid water. ・The system can also provide the distance information between the end-effector and the objects by noncontact. And as a result, it makes possible to improve the efficiency of noncontact-cutting and decontamination work (e.g. using laser and water jet system). |
| 173 | 207 | (IRID reference translation) Underwater laser cutting method | B-2 | IHI Corporation | (IRID reference translation) Since operation of fuel debris removal is carried out in a high dose environment, interfering equipment such as PCV, RPV, piping etc. are cutoff and dismantled by using remote control equipment, and secure the access route for transporting debris. Underwater laser cutting is characterized by “Small cutting reaction force” and ”Cutting steel material in the air /underwater,” and this cutting technology is effective for remote dismantling under the environment of high radiation dose and underwater/in the air. |
| 174 | 208 | (IRID reference translation) Establishment of internal RPV/PCV inspection and debris removal strategy | A-1 | Nippn Nuclear Fuel Development Co., Ltd. | (IRID reference translation) To detect efficiently condition inside the reactor, and to collect and store the verification data of phenomena occurred in each unit, it is important to estimate the various cases for occurred phenomena and establish internal investigation points, method, debris removal plan etc. Therefore, phenomena are required to be verified and investigated from the wide viewpoints, such as fuel/FP behavior, thermal hydraulics, nuclear characteristics and to establish strategies of investigation and removal is necessary. This proposal provides information regarding the establishment of internal investigation plan by assuming various cease for the phenomena occurred in Unit No.1 to No.3 including data collection/storage. |
| 175 | 209 | (IRID reference translation) Characterization of debris properties by ultrasonic sensor based sensor complex | A-2 | 東京工業大学 原子炉工学研究所 木倉研究室 | (IRID reference translation)At the accident of TMI-2 in the U.S., ultrasonic waves were used to identify the condition inside the reactor and it achieved great results. At that time, it was used for the purpose of identifying peripheral object shape, but its signal may identify the fluid state in the reactor by being analyzed by applying signal processing method utilizing our Ultrasonic Velocity Profiler method (UVP method). Environment inside the nuclear reactor is in the severe state of high temperature, high pressure and high radiation dose, but our research know-how for the hardware･software under the difficult requirement that we have been developing will be useful for this investigation. If we can obtain information on the fluid behavior of internal water, we can detect the point of leakage from pressure vessel・containment vessel and estimate temperature distribution around the debris. And then, when inserting sensor in the vessel, condition inside the vessel can be comprehensively observed by using sensor complex that combines not only ultrasonic wave sensor but also other sensors. Also it will be useful for verification of disposal method to be conducted afterward. |
| 176 | 210 | Radiation-tolerant color camera | A-2 | IHI Corporation | ・ Radiation-tolerant color camera(Dose rate:50Gy/h, Total dose:10^5Gy) ・ Dimensions: Maximum height:952mm, Maximum turning diameter:φ555mm ・ Weight: About 85kg ・ Function: Pan, Tilt, Zoom, Focus, Iris, etc. (This camera is using the semiconductor logic element(FPGA, etc.), and superior to general radiation-tolerant camera. For example it can remotely adjust the hue of video.) ・ Light: LED |
| 177 | 211 | (IRID reference translation) Development of remotely operated vehicle for internal PCV/RPV inspection | A-1 | Kanazawa Institute of Technology | (IRID reference translation) To complete decommissioning measures, I proposes Remotely operated vehicle (ROV) corresponding to the key point of PCV/RPV. It is essential to detect melting condition of fuel debris at the bottom of the RPV to establish a concept of decommissioning measures, as well as condition of contaminated water leakage in the S/C and torus room. ROV that meets the requirement of the access route and water level has to be developed to solve these issues. Assuming X100B and X6 for access route, cameras used in the air and underwater, low frequency sonar, high frequency sonar will be used for internal investigation. I propose Archimedes Screw type boat (AS-Boat), swing drive type ROV(SD-ROV), and small series type ROV(AS-ROV) for mechanism to use those investigation tools. These boats are expected to be effective for basic technology of underwater swimming robot to be used for the decommissioning measures and also, its know-how will be able to be applied for the investigation on leakage of underground water of the reactor building and turbine building. |
| 178 | 212 | (IRID reference translation) Study on final disposal method of debris | B-2 | Kikura Laboratory, Research Laboratoy for Nuclear Research, Tokyo Inst. of Technology | (IRID reference translation) As for the disposal of debris caused by the accident of Fukushima Daiichi NPS, although there are many researches were done from the perspective of processing debris mixed with seawater, only a few of them were from the perspective of disposal site. There are two types of final disposal methods, which are the disposal by glass solidification after the reprocessing conducted by Japan and France, and the direct disposal of spent fuel verified by other foreign countries. However, direct disposal by cutting debris itself may be applicable for the debris caused by the accident this time since compositions of impurities are unknown due to the composition of isotope and sea water contamination. Therefore, the both methods of reprocessing･direct disposal shall be discussed considering the advantage and disadvantage of application for the debris removal, and concrete disposal method shall be verified. Then concrete processing method shall be verified based on the results obtained from the discussion. Also, further verification should be done to determine the disposal method including transportation method of debris. |
| 179 | 213 | Radiation-tolerant color camera | B-2 | IHI Corporation | ・ Radiation-tolerant color camera(Dose rate:50Gy/h, Total dose:10^5Gy) ・ Dimensions: Maximum height:952mm, Maximum turning diameter:φ555mm ・ Weight: About 85kg ・ Function: Pan, Tilt, Zoom, Focus, Iris, etc. (This camera is using the semiconductor logic element(FPGA, etc.), and superior to general radiation-tolerant camera. For example it can remotely adjust the hue of video.) ・ Light: LED |
| 180 | 214 | Ultra-high radiation hardness electronics using silicon carbide | B-2 | Saitama University, Japan Atomic Energy Agency, Sanken Electric Co.,Ltd. | In this work, we will perform gamma irradiation to the SiC semiconductor MOS junction diodes and transistors, try to clarify the mechanism of the defect generating at the semiconductor surface or the interface at device junction interfaces, and also verify the durability not only over radiological environment but high temperature and high humidity environments. Then, this research is promoted aiming at the realization of a MOS type semiconductor device that exceeds a few MGy durability (a few hundreds or thousands times as much as Si device durability) in various hard environments based on the knowledge about the acquired radiation trauma. |
| 181 | 215 | Radiation Tolerant Color CID TV Camera | A-2 | Q・I INCORPORATED | -100 times superior to standard CCD/CMOS camera in radiation tolerance and can be widely used under high radiation dose, such as spent fuel inspection and debris inspection, and provide clear and high quality picture (PMOS structure radiation hardened color CID imager is used). -One and only solid-state one-imager color camera in the world can operate under high radiation environment. -Camera unit and Lens unit can be replaced separately and therefore can maintain them easily. -Fully Waterproof and simple design camera head. -Newly developed lens unit (f=16mm) is hardly browning (non-browning high index material is used.) -Zoom function is available (option). |
| 182 | 216 | (IRID reference translation) Transoirtation to the deep underground of Reactor building of Fukushima Daiichi NPS | A-1 | 伊藤 範明 (三井建設株式会社OB) | (IRID reference translation) I hardly have a basic knowledge of Nuclear power station, but based on the supporting document, ”Schematic diagram for Transportation to the underground of Fukushima Daiichi NPS reactor building, the outlines is separating reactor building such as from turbine building, placing it into the package and transporting it to the area at around -1000m underground since there is hard bedrock in the deep underground according to Supporting document 2” Site neighborhood–Site geological structure,” bedrock (granite) at around GL-1000m. For detailed outlines, refer to supporting document 3. |
| 183 | 217 | Radiation Tolerant B/W CMOS TV Camera | A-2 | Q・I INCORPORATED | -Over 100 times superior to standard CCD/CMOS camera in radiation tolerance and can be widely used under high radiation dose, such as spent fuel inspection and debris inspection, and provide clear and high quality picture. -Compact and lightweight by using Radiation hardened B/W CMOS imager. -Camera unit and Lens unit can be replaced separately and therefore can maintain them easily. -Fully Waterproof and simple design camera head. -Zoom function is available. |
| 184 | 218 | Management of fuel debris as a waste | B-1 | French Alternative Energies and Atomic Energy Commission (CEA) | Once retrieved from the reactor, fuel debris will have to be properly conditioned as a waste, and to be stored meeting all the safety requirements. Packaging and storage conditions depend on the physical-chemical properties of the waste (stability, solubility…). It is of paramount important to first estimate these properties on the basis of surrogate samples produced in conditions close to the reactor ones. Based on these properties, a fuel debris management strategy will be proposed (direct packing in canisters, stabilization in a matrix prior to packing, or treatment to meet the safety requirements). |
| 185 | 219 | (IRID reference translation) Internal inspection observation・laser monitoring technology | A-2 | 独立行政法人日本原子力研究開発機構 | (IRID reference translation) Sensing technology that combines observation by fiberscope, ultimate analysis by Laser-induced breakdown spectroscopy, radiation measurement by Scintillators (way of combining is optional). In either combination, access from outside the containment vessel to inside containment vessel will be provided by the transmission by optical fibers. Use of optical fibers for remote sensing will achieve excellent accessibility in narrow space, radiation resistance, water resistance and electromagnetic noise resistance. It can be downsized by complex-type optical fibers. Image of observing point will be taken by the water proof wide angle scope that can adjust its focal distance and be transferred to CCD camera by image fiber, and be forwarded to PC via wireless. Laser-induced breakdown spectroscopy can secure emission intensity that disperses underwater by gas purge function, and abundance ratio for major incore materials including nuclear fuel material such as U,Pu,Zr,Fe,Cr,B can be analyzed. Radiation resistance of optical fibers will be obtained by group OH-basis or F additive. Also, near infrared rays that hardly cause transmission loss even if it is under the radiation environment will be adopted. |
| 186 | 220 | Vehicle type Power Manipulator(V1000) | A-1 | Mitsui Engineering & Shipbuilding Co., Ltd./Wälischmiller Engineering GmbH (Germany) | We suggest the vehicle type power manipulator that can bring the investigation device into RPV/PCV. The vehicle that we suggest can load and hold the investigation device with arm. In case that the investigation device is brought into RPV/PCV, it is necessary to remove the internal object in RPV/PCV. Therefore we think that vehicle have the large movement range and big handling capacity is effective for the investigation working. 【The part of vehicle】 ・Underwater ・Outrigger that support the anti-power of warking used tool 【Powermanipulator】 Capacity：100kg D.O.F of Arm : 6+Hand The movement range of rotation axis:∞ |
| 187 | 221 | Laser cutting in air or under water | B-2 | CEA (French Alternative Energies and Atomic Energy Commission) and Cybernétix | Laser cutting in air or under water devices can be be used to make room before and while corium retrieval |
| 188 | 222 | Washing method of a reactor by the slurry use | B-1 | MASAKATSU UEHARA | (IRID reference translation) I hereby propose the following method. Inject colloid solution (hereinafter called “slurry.”) that contains fine particle consisting mainly of clean glass ingredients which removed organic object into water and adjust concentration to the proper level into the line of cooling water injection cycle, and circulate it by adjusting concentration in incremental steps. In the initial phase of circulation, concentration of slurry is low since it contains high water content to cool down the decay heat of melted fuel debris, but increase concentration incrementally and performs cleaning with increasing flow velocity of slurry so as to polish inside the vessel by its particle. Crack and bore will be filled with particles of adjusted slurry and stop water. When decay heat of melted fuel debris reaches proper quantity of heat, stabilize at the target position by covering the melted fuel debris by increasing the concentration of slurry and viscosity as well as reducing quantity of water. In this stable condition, dismantle the vessel serially and retrieve it with dried or semidried slurry. |
| 189 | 223 | DBD Limited applied knowledge and expertise in management of fuel debris | B-1 | DBD Limited | DBD Limited experts possess extensive knowledge and experience gained from addressing the challenges arising from nuclear facility operations, with a strong track record of delivering innovative solutions that meet our clients’ needs. We are an independent and impartial SME that is capable of providing unbiased support to our clients. DBD experts are adept at providing innovative solutions to difficult problems through decision making, optioneering, and technology selection process. Our flexible and adaptable approach also uniquely positions us to support our international client through our understanding of the cultural, engineering, and working differences that exist within a multinational delivery team and thus creating an environment for successful delivery. |
| 190 | 224 | Radiation tolerant camera using new development devices of cold cathode & photoconductor. | A-2 | FLOVEL Co. ltd. | Many radiation tolerant cameras in the current market use bulky and power consuming image tubes which still perform better than CCD/CMOS under high radiation. These problems of image tube will be solved and the further radiation tolerance will be added by development of a micro vacuum imaging device, tolerant to 100000Gy radiation in accumulation, incorporating the proven photoconductor and new cold cathode addressing technology. This compact device consumes less power without generating heat and improves image quality and reliability. The new radiation tolerant camera using this device and the optical fiber system for remote operations will be developed. These developments are proposed jointly by three companies: Hamamatsu Photonics K.K., Nanox Japan, Inc. and FLOVEL CO., Ltd. |
| 191 | 225 | A compact and simple-scanning laser head using power laser for debris retrieval | B-1 | The Graduate school for the Creation of New Photonics Industries,TOYOKOH, CHUBU Electric Power | (IRID reference translation) This is the technology that fracture and remove debris under water by beam irradiation of high power laser. In this method the fiber laser of kW class will be used as a light source in the building, and this is recently applied in the wide rage such as of metal working head and welding because of rapid acceleration of power increase and cost reduction. This will be transported to the vicinity of debris by optical fibers. Laser beam which is output from small light laser head which has simplified scanning function of laser will fracture the debris finely by heating, melting, and partially transpiring (ablation), and removes fractured debris by drainage function that accompanied. This is based on development of the removal apparatus for laser coating film that intends to be applied for deteriorated bridge in collaboration with Toyokoh. Now we are starting to provide site fabrication with kW class, 100m optical fibers transportation, simplified scan type laser head of about 2kg that is easy to be handled. In collaboration with Chubu Electric Power Co we have started research to apply for the underwater decontamination for normal decommissioning since 2013. |
| 192 | 226 | (IRID reference translation) Manipulator mechanism with high-extension-contraction ratio to bend reversibly for overload | A-2 | Takashi Saito, Akita Prefectural University | (IRID reference translation) This is a telescopic mechanism that bundles together the band-shaped spring steel which can rewind in the bar-shape, and was developed for expansion of application of robot. There are three features as follows : (1)Capable of compactly–stored, (2)Capable of being very long comparing to its original condition, (3)Bend reversibly for the load over the specific level. If combining such as with robot and vehicle, it leads to the expansion of transportation capability/operation range. Also, it can be used individually as a simplified mobile hoisting equipment/remote manipulator. Two basic structures can be selected according to the purpose of use as follows. If the compactness supersedes, use it by folding one band steel once so as that two band steels seem to be bundled, and if strength supersedes, use it just by bundling three band steel. Also, if the strength and high power is required, more band steel can be added and be bundled. We already made a prototype of three-band steel types of 4m and one band steel type of the same bundle of 2m by 5cm-wide band steel. Since it is simple mechanism, such as motorized tape measure, expansion of length and scale, and strength is easy. Patent right has been granted in Japan and Europe, and the applicant owns the patent. |
| 193 | 227 | FUEL DEBRIS REMOVAL WITH DISMANTLING ROBOTS | B-1 | PLEJADES GmbH, INdependent Experts with Consortium Partners | The Consortium under lead of PLEJADES proposes a recovery method based on available technologies and experiences to develop a customized recovery method for Fukushima in about 2 years. The methodology is based on heavy duty dismantling robots conceived for working under very high radiation context. The methodology is sufficient flexible to adapt to unexpected situations. This means that even if not all details are investigated works can be performed. The lead partner has specific experience in organizing this type of projects (e.g. Chernobyl project and others) and the consortium partners including European and Japanese competent companies and organisations will ensure all required capabilities for design, licensing and implementation. |
| 194 | 228 | The fuel debris recovery construction method in a perfect encapsulated type solid | B-1 | Haruo Morishige | CV, RPV, and PRC are filled up with coolants, such as ice and liquid nitrogen, the water which has leaked is frozen.The groundwater which has invaded from the circumference is stopped. Water is poured from temporary piping to about 1/3 in a pedestal. Then all the water surface is covered for the ice which mixed copper and was cooled by liquid nitrogen. Liquid nitrogen is poured in, copper and ice are frozen and a fuel debris is cooled indirectly. It bowls in this solid , and makes a probe go into that drilled pipe. High-temperature vapor, and liquid nitrogen are injected from a probe tip to a fuel debris, and a fuel debris is ground. Gaseous pressure power sends the ground fuel debris to a storage container from the pressure feed pipe in a probe. |