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Report No.

Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 3; Corium/sodium-concrete interaction behavior

Kawaguchi, Munemichi; Uno, Masayoshi*; Konishi, Kensuke; Yamamoto, Ikuo*; Miyahara, Shinya*

We started a project on "Development of Estimation Technology for Availability of Measure for Failure of Containment Vessel in Sodium Cooled Fast Reactor" as a program for R&D for nuclear system, development of basic technology for safety. We planed to develop an evaluation method based on experiments of hydrogen generation and concrete ablation in sodium-concrete reaction. This report shows the plan and a part of the sodium test.



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