Maanshan small-LOCA analysis

Conference · Fri Jan 01 04:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5529639

Chen, C C; Wang, T K; Chiang, S C

According to Maanshan Unit 1 plant probabilistic risk assessment (PRA), the small loss-of-coolant accident (LOCA) S{sub 2}WH is ranked third in frequency among postulated accidents. Maanshan-1 is a 2775-MW (thermal), three-loop Westinghouse pressurized water reactor with large dry containment. The sequence S{sub 2}WH is defined as a small LOCA S{sub 2}, loss of residual heat removal (RHR) cooling W, and loss of low-head safety recirculation H. All the results reported are based on MAAP 3.2 calculations. In addition to a base case study, calculations were made based on changes in the LOCA break area, fan cooler availability, and injection capability (in case C). Comparisons between the base case and other cases can then be used to assess the vessel and containment behavior under various plant conditions. In addition to the above S{sub 2}WH studies, another calculation was performed on the assumption that both high- and low-head injection were unavailable. By PRA definition, this is the S{sub 2}DJ accident (case C). To compare with the S{sub 2}WH accident, the loss of both high- and low-head injections caused core uncovery and vessel failure to occur at an earlier time. The conclusions are summarized.

• OSTI ID: 5529639
• Report Number(s): CONF-881011--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 57
• Country of Publication: United States
• Language: English

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