优化 VVER-440 燃料乏核燃料桶的装载

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
M. Lovecký, J. Závorka
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引用次数: 0

摘要

本文探讨了乏核燃料的管理问题,重点是用于储存和运输 VVER-440 反应堆乏核燃料的两用乏燃料桶。主要目标是通过开发一种由强大工具支持的广泛方法来优化乏燃料桶的装载。利用多重分区策略,较冷的外部燃料组件可以保护辐射源不受较热的内部组件的影响。最近开发的 OPOS-440 计算代码是一种基于粒子通量计算的有效工具。该代码可以优化装载模式,并根据选定的燃料装载量确定乏核燃料容器周围的剂量率。该代码还全面展示了不同燃料组件对剂量率的影响。这些发现对反应堆运行具有现实意义,包括优化乏燃料箱装载和支持已存在的乏燃料箱中新型燃料的许可程序。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Optimizing spent nuclear fuel cask loading for VVER-440 fuel
The paper explores the management of spent nuclear fuel, focusing on dual-purpose spent fuel casks used to store and transport spent nuclear fuel from VVER-440 reactors. The main goal is to optimize spent fuel cask loading by developing an extensive methodology supported by a powerful tool. Using a multiple-zoning strategy, cooler outside fuel assemblies protect radiation sources from the hotter inner assemblies. An effective tool based on adjoint particle flux calculations is the recently developed OPOS-440 calculation code. This code allows for optimizing the loading pattern and determining dose rates surrounding the spent nuclear fuel cask for a selected fuel loading. The code also thoroughly demonstrates how different fuel assemblies affect the dose rate. These findings have real-world implications for reactor operations, including optimizing cask loading and supporting the licensing procedure for novel fuel types in already-existing spent fuel casks.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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