Analysis of a main steam isolation valve closure anticipated transient without scram in a boiling water reactor

Journal Article · Thu Nov 30 23:00:00 EST 1989 · Nuclear Technology; (USA)

OSTI ID:6928087

Liaw, T J; Pan, C; Chen, G S ^[1]; Hsiue, J K ^[2]

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1. National Tsing Hua Univ., Hsinchu (Taiwan). Dept. of Nuclear Engineering
2. Taiwan Power Co., Taipei (TW)

Anticipated transient without scram (ATWS) could be a major accident sequence with possible core melt and containment damage in a boiling water reactor (BWR). The behavior of a BWR/6 during a main stream isolation valve closure ATWS is investigated using the best-estimate computer program, RETRAN-02. The effects of both makeup coolant and boron injection on the reactor behavior are studied. It is found that the BWR/6 behaves similarly to the BWR/2 and BWR/4.

• OSTI ID: 6928087
• Journal Information: Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 88:3; ISSN 0029-5450; ISSN NUTYB
• Country of Publication: United States
• Language: English

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BWR TYPE REACTORS
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VALVES
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WATER MODERATED REACTORS