本文以船用反应堆为研究对象,利用RELAP5/MOD3.2程序建立一维系统模型,对蒸汽发生器给水故障引起的反应堆温度不对称偏环路运行进行计算分析。计算结果表明:蒸汽发生器给水故障时,反应堆压力容器的左、右环路进口冷却剂温差会出现大于10 ℃的情况;当蒸汽发生器维持给水流量小于40%时,反应堆的温度不对称偏环路运行会导致异常环路的蒸汽发生器压力、温度存在较大波动,不利于系统的运行控制和稳定。
This article takes marine reactors as the research object and uses the RELAP5/MOD3.2 program to establish a one-dimensional system model to calculate and analyze the reactor temperature asymmetry partial loop operation caused by the steam generator feed-water failure. The calculation results show that: when the steam generator feed-water fails, the temperature difference between the inlet coolant of the reactor’s left and right loops will be greater than 10 ℃;when the steam generator maintains the feed-water flow rate of lea than 40%, the reactor temperature asymmetric partial loop operation will result in large fluctuations in the steam generator pressure and temperature of the abnormal loop, which is not conducive to the operation control and stability of the system.
2021,43(7): 78-81 收稿日期:2020-07-12
DOI:10.3404/j.issn.1672-7649.2021.07.016
分类号:TL326
作者简介:张鑫(1972-),男,副教授,从事动力装置仿真与安全分析
参考文献:
[1] 张杨伟, 蔡琦, 蔡章生. 船用核动力装置给水完全丧失事故干预效应分析[J]. 船海工程, 2010, 39(1):146-150
ZHANG Yang-wei, CAI Qi, CAI Zhang-sheng. Analysis of intervention effect of complete loss of feed-water for marine nuclear power plant[J]. Marine engineering, 2010, 39(1):146-150
[2] 谢海燕, 蔡琦, 于雷. 船用堆蒸汽发生器给水减少事件运行安全分析[J]. 舰船科学技术, 2009, 31(11):31-33
XIE Hai-yan, CAI Qi, YU Lei. Operational safety analysis of feed-water reduction event of marine reactor steam generator[J]. SHIP SCIENCE AND TECHNOLOGY, 2009, 31(11):31-33
[3] 孔松, 于雷, 袁天鸿, 等. 小型核动力装置自然循环运行特性分析[J]. 原子能科学技术, 2017, 51(12):2143-2148
KONG Song, YU Lei, YUAN Tian Hong, et al. Research on natural circulation characteristic of small nuclear power plant[J]. Atomic Energy Science and Technology, 2017, 51(12):2143-2148
[4] The RELAP5 Code Development Team. RELAP5/MOD3.3 code manual volume[M]. Idaho:Idaho National Engineering Laboratory. 2001:124−202.
[5] 王坤, 董秀臣, 张鑫, 等. 小型压水堆偏环路运行堆芯入口流量分配耦合分析[J]. 舰船科学技术, 2019, 41(11):124-128
WANG Kun, DONG Xiu-chen, ZHANG Xin, et al. Coupling analysis of flow distribution at core inlet of small pressurized water reactor[J]. Ship Science and Technology, 2019, 41(11):124-128
[6] 桂学文, 蔡琦, 邾明亮. 双环路压水堆非对称入口条件下物理-热工特性研究[J]. 原子能科学技术, 2010, 44(S):216-221
GUI Xue-wen, CAI Qi, ZHU Ming-liang. Operation behaviors of pressure water reactor with double loops under asymmetrical inlet conditions[J]. Atomic Energy Science and Technology, 2010, 44(S):216-221