Analysis on containment depressurization under severe accidents for a Chinese 1000 MWe NPP |
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| Affiliation: | 1. School of Mechanical Engineering, Shanghai Jiao Tong University, 800, Dong Chuan Road, Shanghai 200240, China;2. Department of Design Management, Shandong Nuclear Power Co. Ltd, Shandong 265116, China;1. Advance Industrial Science and Technology, National Metrology Institute of Japan, Central 3, 1-1-1, Umezono, Tsukuba, Ibaraki 305-8563, Japan;1. EDF R&D/AMA, 828 Boulevard des Maréchaux, F-91762 Palaiseau Cedex, France;2. IMSIA/Université Paris Saclay, UMR 9219 EDF-CNRS-CEA-ENSTA, 828 Boulevard des Maréchaux, F-91762 Palaiseau Cedex, France;3. 3SR/Université Grenoble Alpes, UMR 5521, Domaine universitaire, BP 53, F-38041 Grenoble Cedex 9, France;4. LMT-Cachan/ENS-Cachan/CNRS/Université Paris Saclay, UMR 8535, 61 avenue du Président Wilson, F-94230 Cachan, France;1. Becker Technologies GmbH, Koelner Strasse 6, 65760 Eschborn, Germany;2. AREVA GmbH, P.O. Box 1109, 91001 Erlangen, Germany;3. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Forschungszentrum, Boltzmannstraße 14, 85748 Garching, Germany;1. State Key Laboratory of Coastal and Offshore Engineering, Dalian University of Technology, Dalian 116024, China;2. Institute of Earthquake Engineering, Dalian University of Technology, Dalian 116024, Liaoning, China;3. China General Nuclear Power Group, Shenzhen 518029, Guangdong, China;1. School of Engineering, Cardiff University, CF24 3AA, Wales, UK;2. School of Engineering, University of Liverpool, Liverpool, L69 3GH, UK;3. Universidad Politécnica de Madrid: José Gutierrez Abascal 2, Madrid, 28006, Spain;4. Department of Engineering and Architecture, University of Trieste, Via A. Valerio 6/1, 34127 Trieste, Italy |
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| Abstract: | Containment depressurization has been implemented for many nuclear power plants (NPPs) to mitigate the risk of containment overpressurization induced by steam and gases released in LOCA accidents or generated in molten core concrete interaction (MCCI) during severe accidents. Two accident sequences of large break loss of coolant accident (LB-LOCA) and station blackout (SBO) are selected to evaluate the effectiveness of the containment venting strategy for a Chinese 1000 MWe NPP, including the containment pressure behaviors, which are analyzed with the integral safety analyses code for the selected sequences. Different open/close pressures for the venting system are also investigated to evaluate CsI mass fraction released to the environment for different cases with filtered venting or without filtered venting. The analytical results show that when the containment sprays can't be initiated, the depressurization strategy by using the Containment Filtered Venting System (CFVS) can prevent the containment failure and reduce the amount of CsI released to the environment, and if CFVS is closed at higher pressure, the operation interval is smaller and the radioactive released to the environment is less, and if CFVS open pressure is increased, the radioactive released to the environment can be delayed. Considering the risk of high pressure core melt sequence, RCS depressurization makes the CFVS to be initiated 7 h earlier than the base case to initiate the containment venting due to more coolant flowing into the containment. |
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