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Sensitivity analysis of the SBLOCA induced severe accident for a natural circulation small modular reactors

  • Longze Li
  • , Jue Wang
  • , Yapei Zhang
  • , G. H. Su
  • Wuhan Second Ship Design and Research Institute
  • Xi'an Jiaotong University

科研成果: 书/报告/会议事项章节会议稿件同行评审

2 引用 (Scopus)

摘要

The natural circulation small modular reactor (NCSMR) is a 330 MW reactor which has no reactor coolant pumps (RCP) and no active safety injection systems at all. The reactor is mainly comprised of the reactor pressure vessel (RPV) with integral pressurizer and steam generator. RPV is enclosed by a vacuumed pressure containment vessel (PCV) and the PCV is submerged in the underground containment pool. A MELCOR model and corresponding input deck are developed for the RPV, PCV, and containment pool. The containment pool takes the role of ultimate heat sink (UHS) in accident situations. The containment pool may crack and leak in some critical accidents as the earthquake, leading to the severe accident of the reactor. A TMI-2 like SBLOCA in the RPV (stuck open RVVs) along with the containment pool crack (loss of ultimate heat sink) is simulated in the work. Some key parameters as the RRVs stuck open fraction, the PCV-SRVs open or not, the containment pool crack position would have large influence on the severe accident sequence. The sensitivity of these parameters to the accident sequence is analyzed in the work. According to the simulation results, the RPV pressure decreased with the RRVs stuck open. The depressurization of RPV accelerated with the RPV-SRV open fraction increase. The PCV pressure increased after that. Two cases as the PCV-SRV open after PCV pressure increase to 5 MPa, and PCV break while the RV did not open, are analysis. The coolant discharge mass flowrate in RPV and PCV were different in two cases, leading to the different degradation situation of the core. Since the containment pool is so important for the accident mitigation, sensitivity analysis is done for the containment pool crack position in the pool. The work will be meaningful in gaining an insight into the detailed process involved. One of the final goals of this work would be to identify appropriate accident management strategies and countermeasures for the potential extreme natural hazard induced severe accidents during the design process of NCSMR.

源语言英语
主期刊名Thermal-Hydraulics and Safety Analyses
出版商American Society of Mechanical Engineers (ASME)
ISBN(电子版)9780791851494
DOI
出版状态已出版 - 2018
活动2018 26th International Conference on Nuclear Engineering, ICONE 2018 - London, 英国
期限: 22 7月 201826 7月 2018

丛书

姓名International Conference on Nuclear Engineering, Proceedings, ICONE
6B

会议

会议2018 26th International Conference on Nuclear Engineering, ICONE 2018
国家/地区英国
London
时期22/07/1826/07/18

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