MELCOR severe accident analysis for a natural circulation small modular reactor

• Published in: Progress in nuclear energy (New series) Vol. 100; no. C; pp. 197 - 208
• Main Authors: Li, Longze, Kim, Tae Woon, Zhang, Yapei, Revankar, Shripad T., Tian, Wenxi, Su, G.H., Qiu, Suizheng
• Format: Journal Article
• Language: English
• Published: Oxford Elsevier Ltd 01-09-2017; Elsevier BV; Elsevier
• Subjects: Accident analysis; Accident conditions; Accidents; Containment vessels; Coolant pumps; Electric power plants; Fission products; Forensic engineering; Light water; Loss of coolant accidents; MELCOR; Natural circulation; Nuclear accidents & safety; Nuclear electric power generation; Nuclear engineering; Nuclear fission; Nuclear power plants; Nuclear reactors; Nuclear safety; SBLOCA; Severe accident; SMR; Steam electric power generation; Studies; SBLOCA; SMR; Severe accident; Natural circulation; MELCOR
• ISSN: 0149-1970; 1878-4224
• DOI: 10.1016/j.pnucene.2017.06.003

A natural circulation small modular reactor (NCSMR) is designed and the severe accident of the NCSMR was analyzed with MELCOR code in this work. The NCSMR is a 330 MWt light water reactor no reactor coolant pumps and no active safety injection systems similar to the design of NuScale reactor. A MELCOR code model was developed for the reactor. The MELCOR model shows consistent results in steady state operation with the design values. The NCSMR severe accident analyzed in this work was induced by the small break loss of coolant accident in the reactor pressure vessel and a crack in the containment pool wall. The decay heat removal system is assumed to fail for the main steam line break. The results indicated that the RPV pressure decreases quickly while the containment pressure increases followed by the opening of reactor vent valves. The core exposes and heat up with the coolant leakage and finally collapsed to the lower plenum, leading to the lower head breach. High temperature core corium quickly broke the relatively thin containment vessel wall, and was discharged to the containment pool floor, leading to the molten corium concrete interaction. The fission products release during the accident process was also analyzed. The severe accident sequence shows that the NCSMR has much longer time duration for the reactor vessel lower head failure to occur compared to conventional commercial nuclear power plant under severe accident conditions. The analysis results help identify appropriate accident management strategies and countermeasures for the potential extreme natural hazard induced severe accidents in NCSMR.
•A natural circulation small modular reactor (NCSMR) is designed.•The NCSMR is modeled with MELCOR.•Severe accident induced by the small break loss of coolant accident and loss of ultimate heat sink is simulated.•The detailed severe accident process and accident sequence are achieved and analyzed.•The results can help identify appropriate accident management strategies and countermeasures in NCSMR severe accident.