近期ROSA/LSTF实验的主要成果和未来计划

T. Takeda, Y. Wada, Y. Sibamoto
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引用次数: 0

摘要

采用安全评价/大型试验装置(ROSA/LSTF)对压水堆(PWR)的事故和瞬态进行了大量试验。最近与经合发组织/NEA国际联合项目有关的研究活动包括通过ROSA和ROSA-2项目进行实验调查,以及在PKL-2、PKL-3、ATLAS和ATLAS-2项目合作下使用热-液压一体化测试设施进行相应测试。根据日本轻水核电站的新监管要求,对LSTF进行的相关整体效应试验的主要结果进行了审查,以便从实验上确定与压水堆事故序列有关的热-水力现象。未来计划使用LSTF进行单独效果试验,以模拟大断裂冷却剂损失事故(LOCA)中应急堆芯冷却系统(ECCS)再循环功能的损失。介绍了近年来利用LSTF进行的多蒸汽发生器管破裂事故恢复、采用堆芯出口温度可靠性事故管理措施的小破裂LOCA以及ECCS冷水注入冷腿下热分层的小破裂LOCA的关键结果和未来计划。此外,LSTF fet的主要结果表明,在高压注入系统完全失效的情况下,具有岩心暴露的广谱LOCA和预期的小断裂LOCA后的瞬态无脱堆。
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Major Outcomes through Recent ROSA/LSTF Experiments and Future Plans
Many experiments have been conducted on accidents and transients of pressurized water reactor (PWR) employing the rig of safety assessment/large-scale test facility (ROSA/LSTF). Recent research activities concerned with the OECD/NEA international joint projects included experimental investigation via the ROSA and ROSA-2 Projects, and counterpart testing with thermal-hydraulic integral test facilities under collaboration of the PKL-2, PKL-3, ATLAS, and ATLAS-2 Projects. Major results of the related integral effect tests (IETs) with the LSTF were reviewed to experimentally identify thermal-hydraulic phenomena involved, regarding the PWR accident sequences in accordance with the new regulatory requirements for the Japanese light-water nuclear power plants. Future separate effect test using the LSTF is planned to simulate loss of emergency core cooling system (ECCS) recirculation functions in a large-break loss-of-coolant accident (LOCA). Key results of the recent IETs utilizing the LSTF and future plans were presented relevant to multiple steam generator tube rupture accident with recovery operation, small-break LOCA with accident management measure on core exit temperature reliability, and small-break LOCA with thermal stratification under cold water injection from ECCS into cold legs. Also, main outcomes of the LSTF IETs were indicated for wide spectrum LOCA with core uncovery and anticipated transient without scram following small-break LOCA under totally failed high-pressure injection system.
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