Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 18; Summary of Development of Detailed Numerical Simulation Methods for Sodium Fire

Aoyagi, Mitsuhiro ; Takata, Takashi ; Ohno, Shuji ; Hamase, Erina ; Uno, Masayoshi*

An R&D project has been conducted to develop detailed numerical simulation methods for sodium fire consequences which is one of risks to put heat and pressure loads to containment vessel of sodium-cooled fast reactor. This contribution summarizes the R&D results involving development of spray combustion and heat transfer models, and a validation of the code through a sodium fire analysis of an upward spray experiment.

Language	:	Japanese
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Meeting title	:	日本原子力学会2017年秋の大会
Held date	:	2017/09
Location (city)	:	札幌
Location (country)	:	日本
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Keywords	:	no keyword
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Cooperating Institute	:	福井大学

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Registration No. : BB20170780
JAEA Abstracts No. :
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