Source term dispersion analysis and construction of the probabilistic dispersion map around the Peach Bottom Unit-2 plant using the ASTEC and JRODOS codes

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-06-01 Epub Date: 2025-02-16 DOI:10.1016/j.anucene.2025.111277
Onur Murat, Fabrizio Gabrielli, Victor Hugo Sanchez-Espinoza
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Abstract

National regulatory authorities and Emergency Preparedness teams require accurate source term predictions to safeguard the public in the event of radiological emergencies, such as severe accidents at Nuclear Power Plants (NPPs). Consequently, reliable assessments of the radiological impacts of hypothetical Severe Accidents (SA) at NPPs are essential. In order to meet this need, a unique and robust platform of simulation codes has been developed at the Karlsruhe Institute of Technology (KIT) to assess the source term data and corresponding radiological consequences of severe accidents. This platform utilizes the CASMO5 code to calculate the fuel inventory in the reactor core and the European reference Accident Source Term Evaluation Code (ASTEC), developed by IRSN, to analyze the severe accident sequence, from initiation to the release of fission products into the environment. The source term data calculated by ASTEC is then used by the JRODOS code, developed by KIT, to assess the radiological effects of the dispersion. In this study, the described platform is used to evaluate the radiological consequences of a Station BlackOut (SBO) scenario at the Peach Bottom Unit-2 NPP. JRODOS analyses use representative dates to assess radiological impacts, as daily evaluations which are considers the possible each starting point computationally impractical. A methodology was developed to assess severe accident consequences for each grid around Peach Bottom Unit-2 NPP. This approach offers a detailed view of the accident’s scope across the region, aiding in the development of appropriate plans for the early and intermediate phases of the accident. Thus, the proposed methodology provides valuable and detailed insights for evaluating emergency preparedness and response actions in the event of a SA at an NPP.
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利用ASTEC和JRODOS代码进行源项色散分析并构建桃底2号机组周围的概率色散图
国家监管机构和应急准备小组需要准确的源项预测,以便在发生放射性紧急情况(如核电站的严重事故)时保护公众。因此,对核电站假设的严重事故(SA)的辐射影响进行可靠的评估是必不可少的。为了满足这一需求,卡尔斯鲁厄理工学院(KIT)开发了一个独特而强大的模拟代码平台,以评估严重事故的源项数据和相应的辐射后果。该平台利用CASMO5代码计算堆芯燃料库存,利用IRSN开发的欧洲参考事故源项评估代码(ASTEC)分析严重事故从发生到裂变产物释放到环境中的顺序。由ASTEC计算的源项数据然后由KIT开发的JRODOS代码用于评估扩散的辐射效应。在本研究中,所描述的平台被用于评估桃底2号机组核电站的站点停电(SBO)情景的辐射后果。JRODOS分析使用有代表性的日期来评估辐射影响,因为每日评估被认为可能的每个起点在计算上是不切实际的。开发了一种方法来评估桃底2号机组核电站周围每个电网的严重事故后果。这种方法提供了整个地区事故范围的详细视图,有助于为事故的早期和中期阶段制定适当的计划。因此,拟议的方法为评价核电站发生安全事故时的应急准备和反应行动提供了宝贵和详细的见解。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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