Development and Application of Core pin-by-pin Calculation of Sub-channel Analysis Code LINDEN
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摘要: 为实现子通道分析软件LINDEN的pin-by-pin计算功能,提高LINDEN软件开展堆芯热工水力分析的计算精度。本研究开发了全堆芯pin-by-pin计算自动建模功能,解决了大型稀疏矩阵的存储和求解问题,开展了157组件反应堆全堆芯pin-by-pin计算及分析。计算结果表明,LINDEN软件可以开展全堆芯pin-by-pin计算,获得堆芯内冷却剂温度分布、偏离泡核沸腾比(DNBR)、质量流速分布等关键热工水力参数的详细分布结果。相邻组件的功率差异会影响组件内的热工水力参数分布。
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关键词:
- 子通道分析 /
- 自动建模 /
- 大型稀疏矩阵 /
- pin-by-pin
Abstract: To realize the pin by pin calculation function of the sub-channel analysis code LINDEN and improve the accuracy of core thermal hydraulic analysis by LINDEN code, an automatic modeling function has been developed for the full core pin-by-pin calculation, and the storage and solution problems of large sparse matrices have been solved. The full core pin-by-pin calculation and analysis of 157 assemblies were carried out. The calculation results indicate that LINDEN can perform full core pin-by-pin calculations, and the detailed distribution results of key thermal hydraulic parameters such as coolant temperature distribution, DNBR, mass flow rate distribution can be obtained. The power difference between adjacent assemblies affects the distribution of thermal hydraulic parameters within the assembly.-
Key words:
- Sub-channel analysis /
- Automatic modeling /
- Large sparse matrix /
- pin-by-pin
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表 1 堆芯布置与关键参数
Table 1. Geometirc Parameters of Test Section
参数 数值 燃料组件数量 157 燃料棒直径/mm 9.5 燃料棒加热长度/m 3.65 燃料棒中心距/mm 12.6 堆芯功率/MW 3113 堆芯流量/(kg·s−1) 12494.1 冷却剂入口温度/℃ 288.3 堆芯出口压力/MPa 15.5 -
[1] 俞冀阳,贾宝山. 反应堆热工水力学[M]. 第二版. 北京:清华大学出版社,2011:200-210. [2] AVRAMOVA M N, SALKO R K. CTF theory manual: ORNL/TM-2016/430[R]. Oak Ridge: Oak Ridge National Lab. , 2016. [3] PÉRIN Y, VELKOV K. CTF/DYN3D multi-scale coupled simulation of a rod ejection transient on the NURESIM platform[J]. Nuclear Engineering and Technology, 2017, 49(6): 1339-1345. doi: 10.1016/j.net.2017.07.010 [4] MAGEDANZ J, PERIN Y, AVRAMOVA M, et al. High-fidelity multiphysics simulation of BWR assembly with coupled TORT-TD/CTF[C]//Proceedings of the Conference on Advances in Reactor Physics - Linking Research, Industry and Education. Knoxville: American Nuclear Society, Inc, 2012. [5] BENNETT A, AVRAMOVA M, IVANOV K. Coupled MCNP6/CTF code: development, testing, and application[J]. Annals of Nuclear Energy, 2016, 96: 1-11. doi: 10.1016/j.anucene.2016.05.008 [6] GUO J J, LIU S C, SHANG X T, et al. Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF[J]. Annals of Nuclear Energy, 2017, 109: 327-336. doi: 10.1016/j.anucene.2017.05.041 [7] 刘宙宇,曹良志. 高保真物理-热工耦合计算方法研究及应用[J]. 原子核物理评论,2020,37(3):797-803. [8] 史敦福,李康,秦桂明,等. 蒙卡中子输运程序JMCT和子通道热工水力程序COBRA-EN耦合计算[J]. 强激光与粒子束,2017,29(3):036007. [9] 白宁,朱元兵,任志豪,等. 子通道分析程序LINDEN的开发与初步验证[J]. 原子能科学技术,2013,47(S1):299-301. [10] 郑成德. 数值计算方法[M]. 北京:清华大学出版社,2010:60-72.