A long-term MAAP 3. 0B analysis of a severe anticipated transient without scram accident in a boiling water reactor

Journal Article · Thu Oct 01 04:00:00 EDT 1992 · Nuclear Technology; (United States)

OSTI ID:6933322

Lee, M; Wu, E C ^[1]

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1. National Tsing Hua Univ., Hsinchu (Taiwan, Province of China). Dept. of Nuclear Engineering

This paper reports that the long-term responses of the reactor coolant system and the containment of a boiling water reactor (BWR) during an anticipated transient without scram (ATWS) initiated by an inadvertent closure of the main steam isolation valves (MSIVs) are analyzed with the MAAP 3.0B computer code. The plant used in the analysis is the Kuosheng nuclear power station, a General Electric BWR6 reactor with a Mark III containment. A comparison of near-term system responses to an MSIV closure ATWS event shows that the MAAP 3.0B code fails to reproduce the detailed thermal-hydraulic results of the sophisticated RETRAN-02 code. The MAAP code, however, makes a reasonable prediction of the timing of major events and core power in the ATWS accident analyzed. The results of a long-term MAAP ATWS analysis show that if the standby liquid control system fails in an MSIV closure ATWS event, the ATWS event might develop into a core melt accident with the containment failing before the core melts.

• OSTI ID: 6933322
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 100:1; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
ATWS
AUTOMATION
BWR TYPE REACTORS
COMPUTER CODES
CONTAINMENT
COOLING SYSTEMS
DEPRESSURIZATION SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
INHIBITION
M CODES
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS