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Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 18; Validation of eutectic reaction model for use in reactor safety analysis code

Liu, X.*; Morita, Koji*; Yamano, Hidemasa   

The purpose of this project is to simulate the eutectic reaction between control rod material, B$$_{4}$$C, and stainless steel, and the relocation behavior of the eutectic compound during a core disruptive accident in a sodium-cooled fast reactor. The authors are developing their physical models for a safety analysis code. In this study, the authors have conducted numerical analyses of the basic experiments for liquifaction of control rod, and examined the applicability of the physical model.

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