SAS4A LMFBR whole core accident analysis code
To ensure that public health and safety are protected even under accident conditions in an LMFBR, many accidents are analyzed for their potential consequences. Extremely unlikely accidents that might lead to melting of reactor fuel and release of radioactive fission products are referred to as hypothetical core disruptive accidents (HCDAs). The evaluation of such accidents involves the simultaneous evaluation of thermal, mechanical, hydraulic and neutronic processes and their interactions. The complexity of this analysis requires the use of large, integrated computer codes which address the response of the reactor core and several important systems. The SAS family of codes, developed at Argonne National Laboratory, provides such an analysis capability. The SAS4A code, the latest generation of this series of codes, has recently been completed and released for use to the LMFBR safety community. This paper will summarize the important new capabilitites of this analysis tool and illustrate an application of the integrated capability, while highlighting the importance of specific phenomenological models.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5986469
- Report Number(s):
- CONF-850410-23; ON: DE85004820
- Resource Relation:
- Conference: ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR CORE DISRUPTION
HEAT TRANSFER
HYDRAULICS
COMPUTER CALCULATIONS
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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