Validation and parametric study of FFRD model in DRACCAR code

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-05 DOI:10.1016/j.anucene.2024.110832
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Abstract

The recent revision of Emergency Core Cooling System (ECCS) regulations in Korea has necessitated the consideration of Fuel Fragmentation, Relocation, and Dispersal (FFRD) phenomena in nuclear reactor safety analyses. Consequently, the Korea Atomic Energy Research Institute (KAERI) has developed and integrated the FFRD model into the domestically licensed safety analysis code, SPACE. Globally, US NRC’s FRAPTRAN and IRSN’s DRACCAR are available for evaluating FFRD phenomena. The FRAPTRAN code incorporates the FFR model, developed by Quantum Technology, while the fuel dispersal model is currently not included. In contrast, the DRACCAR code functions as an integrated analysis platform capable of modeling multi-dimensional thermal, hydraulic, mechanical, and chemical phenomena during a Loss of Coolant Accident (LOCA). This study conducts a thorough examination of the FFRD model in the DRACCAR code and validates its applicability through analysis using the Halden IFA-650 tests. The results demonstrate satisfactory predictive capabilities. Furthermore, a parametric study of key FFRD model parameters enhances the understanding of the FFRD model in the DRACCAR code. The development of detailed physical models in the FFRD model could significantly enhance the performance of the DRACCAR code, warranting the establishment of a comprehensive framework for these advancements. In the future, code-to-code comparisons between the DRACCAR code and other domestically developed integrated analysis platforms will be conducted to investigate various phenomena in depth.

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DRACCAR 代码中 FFRD 模型的验证和参数研究
韩国最近修订了紧急堆芯冷却系统(ECCS)条例,因此有必要在核反应堆安全分析中考虑燃料碎裂、迁移和扩散(FFRD)现象。因此,韩国原子能研究院(KAERI)开发了 FFRD 模型,并将其集成到国内许可的安全分析代码 SPACE 中。在全球范围内,美国核管制委员会的 FRAPTRAN 和 IRSN 的 DRACCAR 可用于评估FRD 现象。FRAPTRAN 代码包含了量子技术公司开发的全燃料流模型,而燃料扩散模型目前尚未包含在内。相比之下,DRACCAR 代码作为一个综合分析平台,能够对失去冷却剂事故(LOCA)期间的多维热、液压、机械和化学现象进行建模。本研究对 DRACCAR 代码中的 FFRD 模型进行了全面检查,并通过使用哈尔登 IFA-650 试验进行分析,验证了该模型的适用性。结果表明其预测能力令人满意。此外,对 FFRD 模型关键参数的参数化研究增强了对 DRACCAR 代码中 FFRD 模型的理解。在 FFRD 模型中开发详细的物理模型可以显著提高 DRACCAR 代码的性能,因此有必要为这些进展建立一个综合框架。今后,将对 DRACCAR 代码和其他国内开发的综合分析平台进行代码间比较,以深入研究各种现象。
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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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