Verification of reliability of the burnup for PWR spent fuel of OPR1000 type

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Donghee Lee , Yongdeog Kim , Kiyoung Kim , Sunghwan Chung , Taehyeon Kim , Taehyung Na
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Abstract

As the saturation of spent fuel pool (SFP) capacity for nuclear power plants starting in 2030 is imminent, the operation of dry storage facilities for spent fuel from pressurized water reactors (PWR) has become urgent. Therefore, it is essential to secure characteristic data on the spent fuel and develop related equipment before these dry storage facilities begin operation. Due to the challenge of inspecting the spent fuel once it is loaded into dry storage casks, it is necessary to identify the characteristics of the spent fuel in advance and secure the information required for the transfer criteria for interim storage and disposal in the future. In particular, among the characteristics data, the burnup of spent fuel is one of the important management items not only for dry storage but also for transportation and disposal. Such burnup varies depending on the operating history, and in reality, nuclear power plants measure and manage the burnup using an in-core instrument (ICI) during operation. This study was conducted to verify the reliability of the burnup of such spent fuel. To this end, comparisons and analyses were conducted among the actual burnup obtained from the power plant, the design burnup calculated from design codes, and the measured burnup of spent fuel actually stored in the storage pool using burnup measuring equipment. This study aimed to establish an evaluation system for the long-term integrity assessment of spent fuel through burnup measurement and comparative analysis for the first time in South Korea, laying the foundation for systematic management.
OPR1000型压水堆乏燃料燃耗可靠性验证
从2030年开始,核电站的乏燃料池(SFP)容量即将饱和,因此,压水堆(PWR)乏燃料干式储存设施的运行变得迫在眉睫。因此,在这些干式储存设施开始运行之前,确保乏燃料的特征数据和开发相关设备至关重要。由于在将乏燃料装入干贮存桶后对其进行检查是一项挑战,因此有必要事先确定乏燃料的特性,并确保今后临时贮存和处置的转移标准所需的信息。特别是乏燃料的燃耗数据,不仅是干贮存的重要管理项目,也是运输和处置的重要管理项目之一。燃耗随运行历史的不同而变化,实际上,核电站在运行过程中使用堆芯内仪表(ICI)测量和管理燃耗。进行这项研究是为了验证这种乏燃料燃耗的可靠性。为此,对电厂实际燃耗、设计规范计算的设计燃耗和使用燃耗测量设备对实际储存在储存池中的乏燃料的实测燃耗进行了对比分析。本研究旨在通过燃耗测量和对比分析,在韩国首次建立乏燃料长期完整性评价体系,为系统化管理奠定基础。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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