Coupling CFAST fire modeling and SAPHIRE probabilistic assessment software for internal fire safety evaluation of a typical TRIGA research reactor

Due to the significant threat of internal fires for the safety operation of nuclear reactors, presumed fire scenarios with potential hazards for loss of typical research reactor safety functions are analyzed by coupling CFAST fire modeling and SAPHIRE probabilistic assessment software. The investiga...

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Bibliographic Details
Published in:Reliability engineering & system safety 2010-03, Vol.95 (3), p.166-172
Main Authors: Safaei Arshi, Saiedeh, Nematollahi, Mohammadreza, Sepanloo, Kamran
Format: Article
Language:English
Subjects:
Applied sciences
CFAST
Core damage frequency
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fire
Fission nuclear power plants
Friction, wear, lubrication
Installations for energy generation and conversion: thermal and electrical energy
Machine components
Mechanical engineering. Machine design
Operational research and scientific management
Operational research. Management science
Reliability theory. Replacement problems
Research reactor
Safety
SAPHIRE
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Summary:Due to the significant threat of internal fires for the safety operation of nuclear reactors, presumed fire scenarios with potential hazards for loss of typical research reactor safety functions are analyzed by coupling CFAST fire modeling and SAPHIRE probabilistic assessment software. The investigations show that fire hazards associated with electrical cable insulation, lubricating oils, diesel, electrical equipment and carbon filters may lead to unsafe situations called core damage states. Using system-specific event trees, the occurrence frequency of core damage states after the occurrence of each possible fire scenario in critical fire compartments is evaluated. Probability that the fire ignited in the given fire compartment will burn long enough to cause the extent of damage defined by each fire scenario is calculated by means of detection-suppression event tree. As a part of detection-suppression event trees quantification, and also for generating the necessary input data for evaluating the frequency of core damage states by SAPHIRE 7.0 software, CFAST fire modeling software is applied. The results provide a probabilistic measure of the quality of existing fire protection systems in order to maintain the reactor at a reasonable safety level.
ISSN:0951-8320
1879-0836
DOI:10.1016/j.ress.2009.09.006