BNPP 3、4号机组同时发生超出设计基础事故的计算分析

A. Anfimov, I. Kirilov, D. Kuznetsov, O. Nikanorov, A. Salyaev
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引用次数: 0

摘要

本文介绍了BNPP 3号机组(BN-600)和4号机组(BN-800)同时发生的超出设计基础事故的计算分析结果。按照NP-001-15的要求,对同时运行的发电机组发生超出设计基础的事故进行安全分析。使用SOCRAT-BN、ANSYS、ORIGEN2和VIBROS 2.2代码进行计算研究。有考虑超出设计基础事故引起的地震影响强度的msk - 64年规模的7分(超过了最大允许地震(MAE)的动力单元3号和相应的动力装置的不美。4)。由于地震影响BNPP的发电单位,发生系统电源,,加上额外的主要设备的故障,导致超出设计基础事故。本文介绍了反应堆装置、机组冷却池和贮存池等非设计基础事故的计算研究和辐射效应评价的结果。超出设计基础事故的计算分析结果表明,放射性释放只发生在BN-600反应堆设施(那里有燃料元件包壳破裂)。同时,事故发生后头几年的预测辐射剂量低于NRB-99/2009决定居民撤离和重新安置的标准。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
CALCULATION ANALYSIS OF SIMULTANEOUSLY OCCURRING BEYOND DESIGN BASIS ACCIDENTS AT POWER GENERATING UNITS № 3 AND 4 OF THE BNPP
The paper presents the results of a computational analysis of simultaneously occurring beyond design basis accidents at power generating units No. 3 (BN-600) and No. 4 (BN-800) of the BNPP. Safety analysis for operating power generating units at the same time occurring beyond design basis accidents is carried out in accordance with the requirements of NP-001-15. Computational studies were performed with the SOCRAT-BN, ANSYS, ORIGEN2, and VIBROS 2.2 codes. There are considered beyond design basis accidents caused by seismic impact with intensity of 7 points on MSK-64 scale (exceeding the maximum allowed earthquake (MAE) for the site of power unit No. 3 and the corresponding MAE for the site of power unit No. 4). As a result of seismic impact at all the power generating units of the BNPP, a loss of system power supply occurs, which, together with additional failures of the main equipment, leads to beyond design basis accidents. The paper presents the results of computational studies of beyond design basis accidents in terms of reactor plant, assembly cooling pond and holding pond and radiation effects assessment. The results of a computation analysis of the beyond design basis accident showed that the release of radioactivity occurs only for the BN-600 reactor facility (where are breaking of the fuel elements cladding). At the same time, the predicted radiation doses for the first years after the accident are lower than the NRB-99/2009 criteria for making a decision on the evacuation and resettlement of inhabitants.
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