Home / Store / Journals / Electronic Articles / Nuclear Technology / Volume 130 / Number 1 / Pages 27-38
Chun-Chang Chao, Chin-Jang Chang
Nuclear Technology / Volume 130 / Number 1 / Pages 27-38
Format:electronic copy (download)
The DPRA-SGTR computer program was written to develop a dynamic event tree for the analysis of a steam generator (SG) tube rupture (SGTR) event. Using the dynamic event tree, a full-scope understanding of the possible responses of a plant following an SGTR event and the related actions with the emergency operating procedures (EOPs) can be analyzed. RELAP5/MOD3.2 was linked to DPRA-SGTR to calculate the thermal-hydraulic response of a Westinghouse three-loop pressurized water reactor at the Maanshan nuclear power plant. One SG tube with a double-ended break was postulated at the beginning of the accident. The plant thermal-hydraulic behaviors, status of the mitigation systems, and operator actions following the EOPs were explicitly modeled in the postulated SGTR. A total of 131 sequences were generated after an SGTR event. Among the 131 sequences, 91 sequences with a frequency sum of 8.5 × 10-6 were stopped either because of low-occurrence frequency (<1 × 10-12) or because the preset mission time was reached (30 000 s after initiating the event). Seven out of the 91 sequences with a frequency sum of 6 × 10-9 were intentionally stopped as a fatal error occurred when RELAP5 was calculating the thermal-hydraulic response.
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