Simulation of the small modular reactor severe accident scenario response to SBO using MELCOR code |
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| Affiliation: | 1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi''an Jiaotong University, Xi''an, 710049, China;2. Nuclear and Radiation Safety Center, Beijing, 100082, China;1. Bechtel Marine Propulsion Corp., Knolls Atomic Power Laboratory, P.O. Box 1072, Schenectady, NY 12301, United States;2. Rensselaer Polytechnic Institute, Gaerttner LINAC Center, 110 8th St., Troy, NY 12180, United States;1. Department of Nuclear Science and Technology, Xi''an Jiaotong University, Xi''an, 710049, China;2. China Nuclear Power Engineering Company, Beijing, 100840, China;1. Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES, Cadarache, BP3, 13115 Saint Paul lez Durance, France;2. Gesellschaft für Anlagen und Reaktorsicherheit (GRS) mbH, Schwertnergasse 1, 50677 Köln, Germany;1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi''an Jiaotong University, Xi''an 710049, China;2. College of Engineering, The University of Wisconsin-Madison, Madison, WI 53706, United States;3. China Academy of Engineering Physics, Beijing 100084, China;1. College of Engineering, The University of Wisconsin-Madison, Madison, WI 53706, United States;2. State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China;3. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;1. SMART Reactor Design Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-Gu, Daejeon 34057, Republic of Korea;2. Thermal Hydraulics and Severe Accident Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-Gu, Daejeon 34057, Republic of Korea |
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| Abstract: | Advanced small modular reactors (SMRs) use different design in the systems, structures, components from large reactors for achieving a high level of safety and reliability. In present work, the SMRs severe accident caused by the station blackout (SBO) was modeled and analyzed using MELCOR code, and the simulation of the accident scenario response to SBO was conducted. Based on the steady state calculation, which agrees well with designed values, we introduced the SBO accident for transient calculation. First, the case of the SBO accident without the passive core cooling system (PXS) was calculated. The progression and scenario in the reactor pressure vessel (RPV) and the containment were simulated and analyzed, including the transient response, cooling capacity and thermal-hydraulic characteristics and so on. The station black-out transient in the SMR can be simulated accurately, and the main failure model in the accident process can be concluded. Then three other cases of the SBO accident with different passive safety systems (core makeup tank (CMT), accumulator (ACC), passive residual heat removal system heat exchanger (PRHR HX), automatic depressurization system (ADS)) of the PXS were calculated respectively, and the results for different passive safety systems were compared. The passive core cooling system can not only provide water to the primary coolant system, but also take away the reactor decay residual heat. So in a station black-out transient, we can get more time for restoring AC power, and effectively prevent the accidents such as Fukushima. |
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| Keywords: | MELCOR SMR Station black-out Severe accident |
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