Full-scale test for repair technology for leakage points inside the primary containment vessel: Reinforcement of suppression chamber support columns (IRID / Hitachi GE Nuclear Energy) (July 31, 2017)

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Title	Full-scale test for repair technology for leakage points inside the primary containment vessel: Reinforcement of suppression chamber support columns (IRID / Hitachi GE Nuclear Energy) (July 31, 2017)
Publisher	International Research Institute for Nuclear Decommissioning
Issued date	2017-07-31
Language	eng
Type	progress report
File Format	HTML
Taxonomy	5-1-3-2 Experimental modelling/analysis
Taxonomy(Computer Assigned)	5-1-3 Reactor processes modelling
Subject/Session_name	Fukushima Daiichi Nuclear Power Station, DECOMMISSIONING, CONTAINMENT SHELLS
Information source	Go to the saved web page
Upper page title	R&D Topics
Related content	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) 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) Investigation inside primary containment vessel (PCV): Development of submersible crawling robot to survey inside PCV of Fukushima Daiichi Power Station Unit 3 (Development by Toshiba) (June 15, 2017) Study on fuel debris retrieval method: "Reactor pressure vessel 1/1 scale model test”, etc. (Development by Hitachi GE Nuclear Energy) (April 2017)
URI	https://f-archive.jaea.go.jp/dspace/handle/faa/195784
collect date(WARP)	2017-10-17

Fukushima Nuclear Accident Archive