Published 1984
| Version v1
Report
Open
Inherent accommodation of unprotected loss-of-flow accidents in LMFBRs
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE84014719.Files
16035120.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- CONF-841105--27
Conference
- Title
- Joint meeting of the American Nuclear Society and the Atomic Industrial Forum.
- Dates
- 11-16 Nov 1984.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16035120
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LMFBR TYPE REACTORS; LOSS OF FLOW; REACTIVITY COEFFICIENTS; REACTIVITY WORTHS; REACTOR KINETICS; REACTOR SAFETY; SPATIAL DISTRIBUTION; SWELLING; TEMPERATURE DISTRIBUTION; THERMAL STRESSES; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; DEFORMATION; DISTRIBUTION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; KINETICS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRESSES