HCCR 毯子失电事故分析

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Hyung Gon Jin, Suk-Kwon Kim, Sungbo Moon, Mu-Young Ahn
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引用次数: 0

摘要

毯式系统是核聚变发电的关键要素,其任务是生产氚和有效消散托卡马克产生的高热通量。韩国正在开发氦冷却陶瓷反射器(HCCR)毯式系统,它是韩国毯式系统中最先进的设计。本文介绍了 HCCR 毯子的 LOOP(场外功率损失)事故分析结果。失电事故是核聚变系统中的假定事件之一。这一事件可能由外部电网的常见故障或现场的电气故障引起。本次安全分析的目的是评估事故发生后 90 秒内启动额外电源对系统温度的影响,并评估与毯式系统热交换器相连的 CCWS(组件冷却水系统)中的滞留冷却剂可带走的热负荷。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Loss of power accident analysis for the HCCR blanket
The blanket system is a crucial element in nuclear fusion power generation, tasked with tritium production and the efficient dissipation of the high thermal flux from the tokamak. Korea is in the process of developing the Helium Cooled Ceramic Reflector (HCCR) blanket, which stands as the forefront design among the nation's blanket systems. This paper presents accident analysis results of LOOP (Loss Of Offsite Power) accident for the HCCR blanket. Loss of power accident is one of the postulated events in the nuclear fusion system. This event may be caused by common failure of the external electrical grids or electrical faults in the site. The objective of this safety analysis is to assess the impact of the activation of an additional power supply within 90 seconds after an accident on the system temperature, and to evaluate the heat load that can be removed by the stagnated coolant in the CCWS (Component Cooling Water System) connected to the heat exchanger of the blanket system.
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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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