Evaluation of proliferation resistance of SMRs with COMPRE methodology assisted by Pu production

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-10-01 DOI:10.1016/j.nucengdes.2024.113615
Kwangho Ju , SeoungHo Jeong , Hosik Yoo
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Abstract

The proliferation resistance (PR) of several small modular reactors (SMR) is investigated in terms of material characteristic and other extrinsic parameters with COMPRE methodology developed by KINAC. In this work, plutonium (Pu) production amount and isotopic yield are newly introduced as key metrics in material characteristic. Their functionalization is performed with a linear regression method based on sparse core depletion data. Nevertheless, a clear discrepancy is observed in Pu buildup and its quality depending on SMR type and core burnup status. Some of the non-light water SMRs exhibit a higher proliferation concern and their PR score trends are clearly different compared to conventional pressurized water reactors (PWR). Other extrinsic parameters are evaluated based on development status of representative SMRs. At present, liquid metal cooled-fast reactor (LMFR) and molten salt reactor (MSR) receive low scores due to their limited technical maturity in reactor design and related I&C equipment. We conclude that distinct safeguards approaches, suitable for a wide range of SMR designs should be developed for commercial use in the near future.
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在钚生产的辅助下,利用 COMPRE 方法评估 SMR 的抗增殖能力
利用 KINAC 开发的 COMPRE 方法,从材料特性和其他外在参数的角度研究了几种小型模块化反应堆(SMR)的抗增殖性(PR)。在这项工作中,新引入了钚(Pu)生产量和同位素产量作为材料特性的关键指标。它们的功能化是通过基于稀疏岩芯损耗数据的线性回归方法实现的。然而,根据 SMR 类型和堆芯燃烧状态的不同,钚的积累及其质量也存在明显差异。一些非轻水 SMR 表现出更高的扩散关注度,其 PR 分数趋势与传统压水堆(PWR)明显不同。其他外在参数则根据具有代表性的 SMR 的发展状况进行评估。目前,液态金属冷却快堆(LMFR)和熔盐堆(MSR)的得分较低,因为它们在反应堆设计和相关 I&C 设备方面的技术成熟度有限。我们的结论是,应在不久的将来开发出适用于各种 SMR 设计的独特保障方法,以供商业使用。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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