高温气冷堆蒸汽发生器换热管破裂事故的进水分析

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-10-08 DOI:10.1016/j.anucene.2024.110968

Hongming Huang , Rongshun Xie , Songsong Liu , Xiaotong Wu , Guotai Cheng , Yaoli Zhang

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引用次数: 0

摘要

蒸汽发生器（SG）换热管破裂（SGTR）是一种特殊的严重事故，会导致水进入反应堆。分析 SGTR 的进水瞬态对验证高温气冷堆（HTGR）的固有安全特性具有重要意义。本文以清华大学设计的 10 兆瓦高温气冷堆为例进行分析。采用 RELAP5/MOD3.2 分别模拟了换热管入口和出口双端铡刀破裂的事故情景。结果表明，进水质量和破裂流速与破裂位置密切相关。排水系统迅速将水排出 SG，有效减轻了事故后果。由于热惯性，平均管内的冷却剂会回流并涌出破裂处，因此必须考虑及时排空平均管的措施。

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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The water ingress analysis on steam generator heat-exchange tube rupture accident of high temperature gas-cooled reactor

Steam generator (SG) heat-exchange tube rupture (SGTR) is a unique and severe accident, which will result in water ingress into the reactor. The analysis on water ingress transient of SGTR holds significant importance for verifying the inherent safety characteristics of high temperature gas-cooled reactor (HTGR). The 10 MW HTGR, designed by Tsinghua University, is exampled to be analyzed in this paper. The accident scenarios of a double-ended guillotine rupture at inlet and outlet of a heat-exchange tube are simulated respectively by RELAP5/MOD3.2. The results show that both water ingress mass and the rupture flow rate are significantly related to the rupture location. The draining system rapidly discharged water from the SG, mitigating effectively the accident consequences. Due to thermal inertia, the coolant inside the average tube refluxes and surges out of the rupture, so it is essential to consider the measures for the timely evacuation of the average tube.

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.