Accurate and reliable reactor thermal hydraulic analysis has important significance for the design and safe operation of the pebble bed modular high temperature gas-cooled reactor. Based on the helium coolant flow and heat transfer process at the core of high temperature gas-cooled reactor, we establish a three-dimensional coupled model by using CFD (computational fluid dynamics) software to simulate the flow and heat transfer of helium coolant at the core. Then the model is verified by comparison of the calculation results with the published results using THERMIX software. The results show that the steady-state results using the three-dimensional model are in agreement with THERMIX calculation data under the rated working conditions, and the relative error is less than 1%. The three-dimensional model simulates the coolant temperature distribution at the core. The research results lay the foundation for the subsequent analysis of complex thermal hydraulic phenomena such as core bypass of high temperature gas-cooled reactor.
ZHANG Shuangbao
,
LI Liangxing
,
XIE Wei
,
WANG Kailin
. Three-dimensional modeling of pebble bed type high temperature gas-cooled reactor core and steady-state thermal hydraulic analysis[J]. Journal of University of Chinese Academy of Sciences, 2020
, 37(2)
: 186
-191
.
DOI: 10.7523/j.issn.2095-6134.2020.02.006
[1] 吴宗鑫,张作义.世界核电发展趋势与高温气冷堆[J].核科学与工程,2000(3):211-219.
[2] Zhou Y, Zhou K, Ma Y, et al. Thermal hydraulic simulation of reactor of HTR-PM based on thermal-fluid network and SIMPLE algorithm[J]. Progress in Nuclear Energy, 2013, 62(8):83-93.
[3] Chen F B, Dong Y J, Zhang Z Y. Post-test simulation of the HTR-10 reactivity insertion without scram[J]. Annals of Nuclear Energy, 2016, 92:36-45.
[4] 李林森,王侃,宋小明.CFD在核能系统分析中应用的最新进展[J].核动力工程,2009,30(S1):28-33.
[5] 彭浩然,孙俊.高温气冷堆堆芯球床的流动与换热分析[J].工程热物理学报,2016,37(5):1076-1083.
[6] Anderson N, Hassan Y, Schultz R. Analysis of the hot gas flow in the outlet plenum of the very high temperature reactor using coupled RELAP5-3D system code and a CFD code[J]. Nuclear Engineering and Design, 2008, 238(1):274-279.
[7] Ferng Y M, Chi C W. CFD investigating the air ingress accident occurred in a HTGR simulation of thermal-hydraulic characteristics[J]. Nuclear Engineering and Design, 2012, 245:28-38.
[8] 梁好玉,武俊梅.压水堆燃料棒束新型定位格架的数值分析[J].中国科学院大学学报,2018,35(2):200-208.
[9] 宋士雄,魏泉,蔡翔舟,等.基于CFD方法的球床式高温气冷堆稳态热工水力分析[J].核技术,2013,36(12):41-47.
[10] 周克峰,周杨平,眭喆,等.基于流动与传热网络的HTR-PM堆内热工水力模拟[J].原子能科学技术,2012,46(8):918-926.
[11] 陈森,刘余,田茂林,等.基于多孔介质模型的压水堆堆芯温场数值模拟[J].核技术,2015,38(9):66-71.
[12] Oh C, Kim E, Schultz R, et al. Comprehensive thermal hydraulics research of the very high temperature gas cooled reactor[J]. Nuclear Engineering and Design, 2010, 240(10):3361-3371.
[13] Wang C, Sun K, Hu L W, et al. Thermal-hydraulic analyses of transportable fluoride salt-cooled high-temperature reactor with CFD modeling[J]. Nuclear Technology, 2016, 196(1):34-52.
[14] 李洋. 高温气冷堆氦气流动及燃料球冷却过程数值模拟[D].北京:北京化工大学,2016.
[15] 陈静,田文喜,韦宏洋,等.基于多孔介质模型的行波堆TP-1堆芯稳态温度场与流场数值模拟[J].原子能科学技术,2013,47(11):1966-1970.
[16] 李良星,李会雄.多尺寸颗粒堆积多孔介质床有效直径研究[J].工程热物理学报,2014,35(9):1785-1788.