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題 名 | Experimental Evaluation of Operator Action in the IIST Facility and Mihama-2 Plant Behavior Comparison on Steam Generator Tube Rupture Incident=蒸汽產生器U型管破事故--IIST實驗評估與電廠案例比較 |
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作 者 | 劉泰健; | 書刊名 | 核子科學 |
卷 期 | 35:6 1998.12[民87.12] |
頁 次 | 頁385-403 |
分類號 | 449.7 |
關鍵詞 | 蒸汽產生器; U型管; 破; IIST實驗評估; 核電廠; Steam generator tube rupture; Accident management; PWR; |
語 文 | 英文(English) |
英文摘要 | The thermal-hydraulic phenomena of steam generator tube rupture (SGTR) incidents in Westinghouse type pressurized water reactor (PWR) have been investigated experimentally at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility. This reduced-height and reduced-pressure (RHRP) test facility was designed to simulate the main features of the unclear steam supply system (NSSS) in Maanshan nuclear power plant (NPP) to validate safety codes and to understand detailed responses which may occur in real plant during th evarious incident transients. The single and multiple SGTR scenarios assumed in this study include the double-ended break of one-, two-, and six-steam generator U-tubes on the Maanshan NPP and follow the related Emergency Operating Procedure (EOP) on the reference plant. This study focuses on the investigation of thermal-hydraulics phenomena and the adequacy of associated EOP to limit primary-to-secondary leakage, particularly, emphasizes on the influence of the number of ruptured tubes on the severity of the incident and the response time available for recovery actions during SGTR. The experimental results were extensively compared with the commercial plant records of the SGTR accident that occurred at the Mihama-2. Through this study, it was found that the key thermal-hydraulic phenomena that characterize the SGTR transients have been successfully simulated in the IIST facility. It was also found that the current EOP functions successfully in terms of terminating the break flow and maintaining adequate core cooling. The adequacy of current EOP in minimizing the radioactive release demands early substantial operator involvement, especially in the multitubes break events. In order to mitigate the consequences of SGTR events, it was found that the time required to isolate faulted SG and to terminate safety injection flows are important. Furthermore, in order to minimize the risk of overfilling, it is suggested that the water level in faulted SG be brained down prior to implementing the cool down process in the reactor coolant system (RCS). |
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