Research on Thermal Safety of Intensive Spent Fuel Dry Storage Facility for Heavy Water Reactor
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摘要: 为解决秦山第三核电有限公司(简称:秦三厂)计划延寿导致乏燃料增加、已有乏燃料干式贮存模块容量不足的问题,在原有的1~6号(QM-400)乏贮模块基础上,研发了密集化乏燃料干式贮存设施(M1型乏贮模块)。与QM-400乏贮模块相比,M1型乏贮模块贮存容量更大,能量密度更高。为论证M1型乏贮模块的热工安全性,采用RELAP5/MOD3程序,根据保守的初始假设条件建立其热工分析模型,对极端气候条件下模块正常运行和事故工况下各区域温度进行了计算,同时采用了三维流体计算流体力学(CFD)程序对RELAP5程序计算结果进行了验证,综合RELAP5程序和CFD程序的计算结果,论证了M1型乏贮模块的热工安全。Abstract: In order to solve the problem that Qinshan No.3 Nuclear Power Co., Ltd. (hereinafter referred to as TQNPC) plans to extend the service life of the nuclear reactor, resulting in the increase of spent fuel and insufficient capacity of existing spent fuel dry storage module, an intensive spent fuel dry storage facility (M1 spent fuel storage module) is developed based on the original No.1~6 (QM-400) spent fuel storage modules. Compared with QM-400 spent fuel storage module, M1 spent fuel storage module has larger storage capacity and higher energy density. In order to demonstrate the thermal safety of M1 spent fuel storage module, RELAP5/MOD3 program is used to establish the thermal analysis model of M1 spent fuel storage module according to the conservative initial assumptions. The temperature of each part of the module under normal operation and accident analysis under extreme weather conditions is calculated. The 3D computational fluid dynamics (CFD) program is used to verify the result of RELAP5 program. The thermal safety of M1 spent fuel storage module is verified according to the calculation results from RELAP5 and CFD programs.
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Key words:
- Spent fuel dry storage module /
- Thermal safety /
- Normal operation /
- Accident condition
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表 1 M1型乏贮模块RELAP5程序热工分析结果汇总
Table 1. Results Summary of Thermal Analysis for M1 Spent Fuel Storage Module by RELAP5 Program
温度 正常运行 一个进气口堵塞 一侧进气口全部堵塞 温度限值 贮存筒最高温度/℃ 93.3 94.3 103.6 350(Q345R) 混凝土最高温度/℃ 侧墙表面:80.7;
顶板表面:86.1侧墙表面:81.6;
顶板表面:89.9侧墙表面:90.2;
顶板表面:94.7正常与预计运行事件(大部分区域)≤120;
事故条件≤120燃料棒束最高温度/℃ 163.3 164.3 173.6 300 燃料篮最高温度/℃ 低于163.3 低于164.3 低于173.6 425 -
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