西安脉冲堆冷却剂大断损事故分析

IF 3.2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-09-27 DOI:10.1016/j.pnucene.2025.106054

Sen Chen, Huaqi Li, Lixin Chen, Leitai Shi, Xiaofei Luo, Xiaoyan Tian, Lei Zhu, Da Li

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引用次数: 0

摘要

利用ISSA-TRIGA软件对西安脉冲堆（XAPR）冷却剂大破断损失严重事故进行了模拟计算。分析了事故中热工参数、燃料棒力学和放射性核素释放的响应特征和结果。结果表明，事故发生后，燃油温度呈现先上升后下降的趋势。当液面下降到上栅格板时，堆芯燃料开始暴露，燃料棒失去冷却，导致燃料温度开始上升。第1环燃料棒包层在1594 s时破裂，第2环和第3环燃料棒包层分别在7642 s和12999 s时破裂。10720s时燃料温度和包层温度分别为1462.3 K和1452.6 K。燃料包壳损坏后，包壳间隙内的核素首先释放，随后部分燃料发生氧化。而氧化反应的平均放热功率相对较小。在事故过程中，燃料温度未超过熔点，燃料未发生大规模失效。本文的计算结果有助于理解XAPR冷却剂大破断损失事故过程，为后续事故的缓解提供重要指导。

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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Analysis of Xi'an pulsed reactor large break loss of coolant accident

The Xi'an pulsed reactor (XAPR) severe accident caused by large break loss of coolant was modeled and computed by using ISSA-TRIGA program. The response characteristics and results of thermal hydraulic parameters, fuel rod mechanics and radionuclide release in the accident were analyzed. The results implied that the fuel temperature tend to rise firstly and then to decrease after the accident occurred. When the liquid level dropped to the upper grid plate, the core fuel began to be exposed and the fuel rod lost cooling, causing the fuel temperature start to rise. The first ring fuel rod clad was damaged at 1594 s, and the second and third ring fuel rod clad ruptured at 7642 s and 12999 s, respectively. The maximum fuel temperature and cladding temperature were 1462.3 K and 1452.6 K at 10720 s, respectively. After the fuel clad damaged, the nuclides in the cladding gap were released firstly, and part of fuel was oxidation subsequently. However, the average heat release power of the oxidation reaction was relatively small. In the process of the accident, the fuel temperature did not exceed its melting point and the fuel did not occur large-scale failure. The calculation results in this paper could be helpful for understanding the large break loss of coolant accident process of XAPR and provide important guidance for the subsequent accident mitigation.

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.