Comparative study of a boron dilution scenario in VVER reactors |
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| Affiliation: | 1. Department of Mechanical and Nuclear Engineering, Nuclear Engineering Program, The Pennsylvania State University, 231 Sachett Building, University Park, PA 16802, USA;2. Research Center Rossendorf Inc., Institute for Safety Research, D-01314 Dresden, Germany;1. Department of Nuclear Engineering and Technology, School of Energy and Power Engineering, Huazhong University of Science and Technology, Wuhan 430074, China;2. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;1. Hungarian Academy of Sciences Centre for Energy Research, 1525 Budapest 114, P.O. Box 49, Hungary;2. Paks Nuclear Power Plant, 7031 Paks, P.O. Box 71, Hungary;1. Department of Nuclear Engineering, Faculty of Advanced Sciences and Technologies, University of Isfahan, Isfahan, Iran;2. Department of Energy Engineering, Sharif University of Technology, Tehran, Iran;1. Oral and Maxillofacial Department, Dental Faculty, King Saud University, Riyadh, Saudi Arabia;1. Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology, Ilkovicova 3, 812 19 Bratislava, Slovakia;2. Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, Gansu 730000, China;3. Institute of Physics of the Czech Academy of Sciences, Na Slovance 1999/2, 182 21 Prague, Czech Republic |
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| Abstract: | Subsequent studies have identified many scenarios, which can lead to reactivity excursions due to boron dilution. The comparative study, presented in this paper, deals with the so-called “restart of the first reactor coolant pump’’ scenario and its reactor-dynamic consequences for both Russian designed VVER reactor types, VVER-440 and VVER-1000. The transient simulations were performed using the three-dimensional core dynamics code DYN3D. The DYN3D modeling features, including recent developments, as well as the cross-section methodology involved in these calculations, are described. The analyzed accident scenario is outlined together with the assumptions made. The results of core response in this boron dilution accident for both VVER reactors are compared within the ranges, determined by the two reactivity values of interest: the criticality limit and the reactivity initiated accident (RIA) limit. |
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