热工水力系统分析程序Courant条件计算方法研究

李江宽; 黄涛; 林萌; 王旭; 陈俊杰

doi:10.13832/j.jnpe.2021.04.0063

热工水力系统分析程序Courant条件计算方法研究

doi: 10.13832/j.jnpe.2021.04.0063

李江宽^1,,
黄涛²,
林萌^1, ,,
王旭¹,
陈俊杰²

1.
上海交通大学核科学与工程学院，上海，200240
2.
中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213

基金项目: 十三五核能开发科研项目“基于深度学习神经网络人工智能的船用核动力装置故障诊断技术研究”

详细信息

作者简介:
李江宽（1993—），男，博士研究生，现主要从事热工水力及故障诊断方面研究，E-mail: lijiangkuan@sjtu.edu.cn

通讯作者:
林　萌，E-mail: linmeng@sjtu.edu.cn

中图分类号: TL334
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- 被引次数: 0
出版历程
- 收稿日期: 2020-07-01
- 修回日期: 2021-03-31
- 刊出日期: 2021-08-15

Study on Calculation Method of Courant Limit in Thermal Hydraulic System Analysis Code

1.
School of nuclear science and engineering, Shanghai Jiao Tong University, Shanghai, 200240, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 为分析采取不同Courant条件计算方法对反应堆热工水力系统分析程序计算速度和计算准确性的影响，研究了2种Courant条件计算方法：综合法与分组法，分析了2者的计算原理，并分别采取这2种方法对压水堆满功率稳态工况和大破口事故工况进行计算。结果表明，稳态工况下2种方法的程序计算结果无明显差异；在速度场变化剧烈的大破口事故工况下，综合法可以取得更加准确的计算结果但耗时较多，分组法可以取得更快的计算速度但计算准确性较低。
- 热工水力 /
- 系统程序 /
- Courant条件 /
- RELAP5
Abstract: In order to analyze the influence of different Courant limit calculation methods on the calculation speed and accuracy of reactor thermal hydraulic system analysis code, two kinds of Courant limit calculation methods were studied: synthesis method and grouping method. The calculation principles of the two methods were analyzed, and the two methods were adopted to calculate the steady-state condition and large break loss of coolant accident condition of a PWR respectively. The results show that there is no significant difference between the two methods in steady-state condition; in the case of large break loss of coolant accident with drastic change of velocity field, the synthesis method can obtain more accurate calculation results, but it takes more time, and the grouping method can obtain faster calculation speed, however its calculation accuracy is lower.
- Thermal hydraulic /
- System code /
- Courant limit /
- RELAP5

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图 1 满功率稳态工况计算性能参数

Figure 1. Calculation Performance Parameters under Full Power Steady State Condition

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图 2 大破口工况计算性能参数

Figure 2. Calculation Performance Parameters under Large Break Loss of Coolant Condition

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图 3 堆芯出口压力对比

Figure 3. Comparison of Core Outlet Pressure

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图 4 破口流量对比

Figure 4. Comparison of Flow at Break

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参考文献(5)

[1]	刘志弢,秦本科,解衡,等. 压水堆核电站热工水力系统程序的研发现状与趋势[J]. 原子能科学技术,2009, 43(11): 966-972.
[2]	The RELAP5 Code Development Team. RELAP5/ Mod3.3 Code Manual, Volume I: Code Structure, System Models and Solution Methods, NUREG/CR-5535, Revision 1[M]. Idaho: INEEL, 2001: 15-74.
[3]	王强,高璞珍,王忠乙,等. 低压高过冷度下自然循环流动不稳定性实验研究[J]. 原子能科学技术,2018, 52(5): 822-828.
[4]	刘新凯,刘建阁,彭敏俊. 基于RELAP5程序的直管式直流蒸汽发生器敏感性分析[J]. 原子能科学技术,2012, 46(9): 1088-1096.
[5]	MAHAFFY J H. Numerics of codes: stability, diffusion, and convergence[J]. Nuclear Engineering and Design, 1993, 145(1-2): 131-145.