Inherent accommodation of unprotected loss-of-flow accidents in LMFBRs
Conference
·
OSTI ID:6236629
Inherent safety is a major focus of attention in fast reactor design. Extensive efforts have been given to utilizing intrinsic characteristics of sodium-cooled reactors to enhance the plant's ability to accommodate even the most unlikely accidents, such as loss-of-flow (LOF) with failure to scram. The renewed interest in the pool concept partially reflects this new direction. The reintroduction of metal fuel also opens a new frontier for fast reactor safety technology. This study explores the potential of the metal fuel in achieving designs which are inherently safe against unprotected LOF accidents. The study is conducted using the SASSYS code and is based on an 1000 MWe pool design.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6236629
- Report Number(s):
- CONF-841105-27; ON: DE84014719
- Country of Publication:
- United States
- Language:
- English
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· Trans. Am. Nucl. Soc.; (United States)
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