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 pressurize r 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. So me 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 d id not open, are analysis. The coolant discharge mass flo wrate 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.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5149-4
PROCEEDINGS PAPER
Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors Available to Purchase
Longze Li,
Longze Li
Wuhan 2nd Ship Design and Research Institute, Wuhan, China
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Jue Wang,
Jue Wang
Wuhan 2nd Ship Design and Research Institute, Wuhan, China
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Yapei Zhang,
Yapei Zhang
Xi'an Jiaotong University, Xi'an, China
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G. H. Su
G. H. Su
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Longze Li
Wuhan 2nd Ship Design and Research Institute, Wuhan, China
Jue Wang
Wuhan 2nd Ship Design and Research Institute, Wuhan, China
Yapei Zhang
Xi'an Jiaotong University, Xi'an, China
G. H. Su
Xi'an Jiaotong University, Xi'an, China
Paper No:
ICONE26-82267, V06BT08A047; 7 pages
Published Online:
October 24, 2018
Citation
Li, L, Wang, J, Zhang, Y, & Su, GH. "Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06BT08A047. ASME. https://doi.org/10.1115/ICONE26-82267
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