SAFER03 and TRAC-BD1 Analyses of a ROSA-III Large-Break Experiment on a Boiling Water Reactor
作者:
ItoyaSeihiro,
KatoMasami,
AbeNobuaki,
NagasakaHideo,
期刊:
Nuclear Technology
(Taylor Available online 1987)
卷期:
Volume 77,
issue 1
页码: 32-45
ISSN:0029-5450
年代: 1987
DOI:10.13182/NT87-A33949
出版商: Taylor&Francis
数据来源: Taylor
摘要:
AbstractSimulation tests of a boiling water reactor (BWR) loss-of -coolant accident (LOCA) caused by a double-ended guillotine break of a recirculation pump suction line were carried out with the rig of safety assessment III (ROSA-III) test facility at the Japan Atomic Energy Research Institute. SAFER03 and TRAC-BD1 analyses with the ROSA-III test data have been performed to assess predictive capability for the large-break LOCA thermal-hydraulic response of a BWR. The analytical results indicate that SAFER03 and TRAC-BD1 predicted key phenomena very well. Furthermore, it was confirmed that SAFER03 predicted higher peak cladding surface temperature than the test data due to the conservative thermal-hydraulic model.
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