新型mw级紧凑型核电系统被动余热排出系统的设计与分析

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Leqi Yuan, Junli Gou, Zhenlan Wang, Bo Zhang, Jianqiang Shan
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引用次数: 0

摘要

热管冷却堆具有设计紧凑、结构简单、安全性高等特点,是无人潜航器的理想动力源。然而,散热器损失事故可能导致反应堆损坏,需要一个被动余热排出系统(PRHRS)进行应急冷却。本研究提出了一种新型紧凑型热管反应器,该反应器采用自然循环冷却热管绝热段。利用稳态CFD仿真对结构进行了优化,并在FORTRAN语言中编写了瞬态分析程序,并用CFD结果进行了验证。研究结果显示,事故发生后,燃料温度立即急剧上升,随后随着反应堆的自然循环冷却,燃料温度下降。在整个事故过程中,组件温度保持在允许的范围内,燃料和热管的最高温度分别不超过965.13 K和972.5 K。PRHRS冷却水未发生沸腾。这证实了PRHRS有效地去除了余热,确保了反应堆在稳态和事故条件下的安全,并为新型兆瓦级紧凑型热管反应堆的设计奠定了基础。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system
The heat pipe-cooled reactor is an ideal power source for unmanned underwater vehicles (UUVs) due to its compact design, simple structure, and high safety features. However, a heat sink loss accident may lead to reactor damage, requiring a passive residual heat removal system (PRHRS) for emergency cooling. This study presents a novel compact heat pipe reactor with a PRHRS that uses natural circulation to cool the heat pipes' adiabatic sections. A steady-state CFD simulation optimized the geometry, and a transient analysis code was developed in FORTRAN and validated with CFD results. The findings show a sharp increase in fuel temperature immediately after the accident, followed by a decrease as natural circulation cools the reactor. Throughout the accident, component temperatures stayed within permissible limits, with the maximum fuel and heat pipe temperatures not exceeding 965.13 K and 972.5 K, respectively. No boiling occurred in the PRHRS cooling water. This confirms that the PRHRS effectively removes residual heat, ensuring reactor safety during both steady-state and accident conditions, and lays the groundwork for the design of new MW-class compact heat pipe reactors.
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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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