Thinning behavior of solid boron carbide immersed in molten stainless steel for core disruptive accident of sodium-cooled fast reactor

Author:

Emura Yuki1,Takai Toshihide1,Kikuchi Shin1,Kamiyama Kenji1,Yamano Hidemasa1ORCID,Yokoyama Hiroki2,Sakamoto Kan2

Affiliation:

1. Sector of Fast Reactor and Advanced Reactor Research and Development, Japan Atomic Energy Agency (JAEA) Ibaraki, Japan

2. Research Department, Nippon Nuclear Fuel Development Co. Ltd. (NFD), Ibaraki, Japan

Funder

Ministry of Economy, Trade and Industry

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference17 articles.

1. Elimination of recriticality potential for the Self-Consistent Nuclear Energy System

2. A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention

3. Demonstration of Control Rod Holding Stability of the Self Actuated Shutdown System in Joyo for Enhancement of Fast Reactor Inherent Safety

4. Yamano H, Takai T, Furukawa T, et al. Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (1) Project overview. Proceedings of the International Nuclear Fuel Cycle Conference 2019 (GLOBAL2019); Seattle, WA; 2019. No. 29833.

5. Reaction Behavior of B4C Absorber Material with Stainless Steel and Zircaloy in Severe Light Water Reactor Accidents

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