Containment transient analysis for postulated accident consequences assessment. [LMFBR]
Conference
·
OSTI ID:7325305
The paper presents a series of parametric studies of LMFBR containment building temperature and pressure transients associated with hypothetical melt-through of a reactor vessel. These studies, based on a 400 Mw/sub t/ fast reactor, were made with CACECO code. The parametric studies examine a series of structural and phenomenological variations, including effects of containment work space cooling system, effects of utilization of heat transport cell structural masses as passive heat absorbers, effects of cell liner failures, and finally, effects of hydrogen recombination. The calculations utilize recently acquired experimental data on water release from concrete by heating, and on autocatalytic recombination of hydrogen and oxygen in a postulated LMFBR containment environment under accident conditions.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-2170
- OSTI ID:
- 7325305
- Report Number(s):
- HEDL-SA-854; CONF-761001-36
- Country of Publication:
- United States
- Language:
- English
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· Nucl. Technol.; (United States)
·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
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CONTAINMENT BUILDINGS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
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210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT BUILDINGS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
STRESSES
TEMPERATURE DISTRIBUTION
TEMPERATURE GRADIENTS
TRANSIENTS