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 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Onur Murat, Fabrizio Gabrielli, Victor Hugo Sanchez-Espinoza
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引用次数: 0

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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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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