TOP > R&D Topics

Full-scale testing of PCV Leakage Point Repairing Technology : Full-scale testing of Water Stoppage Technology by Filling in Suppression Chamber (S/C) [IRID / TOSHIBA] (June 24, 2017)

Jun.24,2017

IRID is engaged in the ongoing development of technology for repairing leakage points in Primary Containment Vessels (PCVs), under a project sponsored by the Ministry of Economy, Trade and Industry (METI) for the FY 2016–2017 period, aimed at the decommissioning of the Fukushima Daiichi Nuclear Power Station (NPS). As part of this project, IRID conducted tests to stop water leakage in the suppression chamber (S/C) by injecting concrete.

Development of technology for criticality control in fuel debris retrieval: Development of “critical approach monitoring method” using Kyoto University Critical Assembly (KUCA) (June 21, 2017)

Jun.21,2017

It is confirmed through the monitoring system that fuel debris is not currently in a critical state. Since the shape of fuel debris and water level may change during fuel debris retrieval in the future, the possibility of criticality configuration is considered to be very small. However, we are promoting development of sub-criticality monitoring technology and criticality prevention technology to ensure prevention of criticality, and also safely terminate criticality, even if it occurs.

Study on Fuel Debris Retrieval Method: “Reactor Pressure Vessel 1/1 Scale Model Test”, etc. [Development by Hitachi GE Nuclear Energy] (April 2017)

Apr.17,2017

As part of its R&D efforts for the decommissioning of the Fukushima Daiichi Nuclear Power Station (NPS), the IRID (development by Hitachi GE Nuclear Energy) is involved in developing fundamental technologies for the retrieval and removal of fuel debris and internal reactor structures, and subsidizing costs for the Decommissioning and Contaminated Water Management Project.

Development of Robot “PMORPH” for Investigation inside Unit 1 Primary Containment Vessel (PCV) (Investigation outside Pedestal Basement: B2 Investigation) [Developed by IRID and Hitachi GE Nuclear Energy] (February 3, 2017)

Feb.03,2017

The “PMORPH”, developed by IRID and Hitachi-GE Nuclear Energy, was presented to the media on February 3. The device, equipped with a dosimeter and underwater camera, will be used to investigate outside the Unit 1 pedestal basement in the PCV, in which fuel debris may have spread to, towards decommissioning TEPCO’s Fukushima Daiichi Nuclear Power Station (NPS).

Full-scale Testing of Technology for Repairing PCV Leakage Points
Full-scale Testing of Strengthening Technology for Suppression Chamber (S/C) Support Columns [IRID/Hitachi GE Nuclear Energy] (November 29, 2016)

Nov.29,2016

IRID is engaged in ongoing development of technology for repairing leakage points in the Primary Containment Vessel (PCV) under a project sponsored by the Ministry of Economy, Trade and Industry (METI) for the FY2016-2017 period towards the decommissioning of the Fukushima Daiichi Nuclear Power Station.

Development of Repair Technology for Water Leakage Sections in PCV Testing Concrete Injection Technology for Water Leak Stoppage Treatment inside Suppression Chamber Using Full-Scale Mock-up Facility [Led by TOSHIBA]. (October 15, 2016)

Oct.15,2016

IRID is advancing the development of repair technology for water leakage sections in the Primary Containment Vessel (PCV) under a project led by Ministry of Economy, Trade and Industry (METI) in FY 2016-FY 2017 towards the decommissioning of the Fukushima Daiichi Nuclear Power Station (NPS). As a part of this project, a method of injecting concrete to repair water leakage points inside suppression chamber (S/C), a structure that lies at the lower part of the PCV, is currently being examined.

Completion of Preparation for Full-Scale Test Facility Simulating the Lower Part of the PCV and Future Test Plans (October 13, 2016)

Oct.13,2016

A full-scale mock-up facility* is now ready for testing purposes to establish technology for repairing water leakage points in the lower part of the Primary Containment Vessel (PCV).

* This test facility simulates vent pipes, the suppression chamber (S/C), and torus room wall found in the lower part of the PCV in Fukushima Daiichi Nuclear Power Station (NPS) Unit 2. The facility is of full-scale size, but represents a 1/8 portion of the circular S/C.