石墨慢化通道式熔盐堆的稳态热工水力计算模型
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摘要
针对石墨慢化通道式熔盐堆的堆芯结构,基于COMSOL Multiphysics程序和MATLAB程序建立了堆芯稳态热工水力学计算模型。该模型对堆芯内固体区域的温度分布采用三维热传导方程进行模拟,对通道内熔盐温度采用一维单相流体模型进行计算。固体区域与熔盐通过熔盐通道壁面的对流换热边界建立热耦合。该模型基于平行通道压力损失相等的原则,分配堆芯内各熔盐通道的流量。通过对比RELAP5程序的计算结果,验证了模型对温度和流量分配计算的正确性。针对2 MWt液态燃料熔盐堆的一种概念设计,分析了堆芯内三维温度分布和通道间流量分配。该模型可精确计算通道式熔盐堆堆芯内稳态温度分布和流量分配,对堆芯的热工水力学设计具有重要意义。
Based on COMSOL Multiphysics and MATLAB software, a three-dimensional thermal-hydraulic model was developed for the graphite-moderated channel type molten salt reactor(MSR). The temperature distribution in the solid region was calculated with a three-dimensional heat conduction equation. The heat transfer in the molten salt was modelled by the one-dimensional single-phase flow model. The thermal coupling of fuel salt and solid region was set up through the convective heat transfer boundary condition at the surface of fuel channel. The mass flow rate in each fuel channel was calculated based on the assumption of equal pressure drop over all channels. In terms of temperature and mass flow rate distribution calculations, the result from this thermal-hydraulic model is consistent with that from the RELAP5 code. With the aid of this model, the temperature and mass flow rate distributions in the 2 MWt MSR were analyzed. This thermal-hydraulic model can be used to precisely analyze the temperature and mass flow rate distributions of the channel type molten salt reactor, which is quite useful in the thermal-hydraulic design.
Based on COMSOL Multiphysics and MATLAB software, a three-dimensional thermal-hydraulic model was developed for the graphite-moderated channel type molten salt reactor(MSR). The temperature distribution in the solid region was calculated with a three-dimensional heat conduction equation. The heat transfer in the molten salt was modelled by the one-dimensional single-phase flow model. The thermal coupling of fuel salt and solid region was set up through the convective heat transfer boundary condition at the surface of fuel channel. The mass flow rate in each fuel channel was calculated based on the assumption of equal pressure drop over all channels. In terms of temperature and mass flow rate distribution calculations, the result from this thermal-hydraulic model is consistent with that from the RELAP5 code. With the aid of this model, the temperature and mass flow rate distributions in the 2 MWt MSR were analyzed. This thermal-hydraulic model can be used to precisely analyze the temperature and mass flow rate distributions of the channel type molten salt reactor, which is quite useful in the thermal-hydraulic design.
引文
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[12] ORNL. SCALE: A modular code system for performing standardized computer analyses for licensing evaluations[R]. USA: ORNL, 2005.
[2] SCOTT D, GRINDELL A G. Components and systems development for molten salt breeder reactors[R]. USA: ORNL, 1967.
[3] ZHANG D L, QIU S Z, LIU G L, et al. Steady thermal hydraulic analysis for a molten salt reactor[J]. Nuclear Science and Techniques, 2008, 19(3): 187-192.
[4] 郭张鹏,张大林,肖瑶,等. 物理-热工耦合计算方法在熔盐堆稳态分析中的应用[J]. 原子能科学技术,2013,47(11):2 071-2 076. GUO Zhangpeng, ZHANG Dalin, XIAO Yao, et al. Application of coupled neutronics/thermal-hydraulics computational method for steady-state analysis of molten salt reactor[J]. Atomic Energy Science and Technology, 2013, 47(11): 2 071-2 076(in Chinese).
[5] KREPEL J, ROHDE U, GRUNDMANN U, et al. DYN3D-MSR spatial dynamics code for molten salt reactors[J]. Annals of Nuclear Energy, 2007, 34(6): 449-462.
[6] 司胜义,陈其昌,卑华,等. 新型钍基熔盐堆多物理计算模型及分析[J]. 强激光与粒子束,2017,29(1):71-78. SI Shengyi, CHEN Qichang, BEI Hua, et al. Modeling and simulation of redesigned thorium molten salt reactor[J]. High Power Laser and Particle Beams, 2017, 29(1): 71-78(in Chinese).
[7] COOKE J W, COX B. Forced-convection heat-transfer measurements with a molten fluoride mixture flowing in a smooth tube[R]. USA: ORNL, 1973.
[8] 李磊,张志俭. 并联通道瞬态流量分配方法研究[J]. 核动力工程,2010,31(5):97-101. LI Lei, ZHANG Zhijian. Research on transient flux distribution in parallel channels[J]. Nuclear Power Engineering, 2010, 31(5): 97-101(in Chinese).
[9] Introduction to COMSOL multiphysics[M]. [S. l.]: [s. n.], 2016.
[10] FERRAGUT M P, WAGNER R J, ALLISON C M. The development of RELAP5/SCDAPSIM/MOD4.0 for advanced fluid systems design and analysis[C]//International Conference on Nuclear Engineering. [S. l.]: [s. n.], 2015.
[11] TMSR. 2 MW液态燃料熔盐实验堆深化概念设计[R]. 上海:中国科学院上海应用物理研究所,2016.
[12] ORNL. SCALE: A modular code system for performing standardized computer analyses for licensing evaluations[R]. USA: ORNL, 2005.