Structural and containment response to LMFBR accidents
Conference
·
OSTI ID:6433192
The adequacy of the containment of fast reactors has been traditionally evaluated by analyzing the response of the containment to a spectrum of core disruptive accidents. The current approach in the U.S. is to consider fast reactor response to accidents in terms of four lines of assurance (LOAs). Thus, LOA-1 is to prevent accidents, LOA-2 is to limit core damage, LOA-3 is to control accident progression and LOA-4 is to attenuate radiological consequences. Thus, the programs on the adequacy of containment response fall into LOA-3. Significant programs to evaluate the response of the containment to core disruptive accidents and, thereby, to assure control of accident progression are in progress. These include evaluating the mechanical response of the primary system to core disruptive accidents and evaluating the thermal response of the reactor structures to core melting, including the effects this causes on the secondary containment. The analysis of structural response employs calculated pressure-volume-time loading functions. The results of the analyses establish the response of the containment to the prescribed loadings. The analysis of thermal response requires an assessment of the distribution and state of the fuel, fission products and activated materials from accident initiation to final disposition in a stable configuration.
- Research Organization:
- Argonne National Lab., IL (USA); Hanford Engineering Development Lab., Richland, WA (USA); General Electric Co., Sunnyvale, CA (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6433192
- Report Number(s):
- CONF-781022-27
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
CALCULATION METHODS
CONTAINMENT
CONTAINMENT SYSTEMS
DYNAMIC LOADS
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
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REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
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