Major Outcomes through Recent ROSA/LSTF Experiments and Future Plans
Major Outcomes through Recent ROSA/LSTF Experiments and Future Plans作者机构：Nuclear Safety Research Center Japan Atomic Energy Agency Ibaraki Japan
出 版 物：《World Journal of Nuclear Science and Technology》 (核科学与技术国际期刊（英文）)
年 卷 期：2021年第11卷第1期
页 面：17-42页
学科分类：08[工学] 082701[工学-核能科学与工程] 0827[工学-核科学与技术]
主 题：PWR ROSA/LSTF LOCA ECCS Integral Effect Test
摘 要：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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