3D Numerical Simulation on Bypass Flow in Pebble-Bed High-Temperature Gas-Cooled Reactor

LIU Wei; SHI Jin; SHAO Jikai; YU Shangzhen; GUO Jinsong; LI Xuelin; LI Zengyao

doi:10.7652/xjtuxb202408016

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3D Numerical Simulation on Bypass Flow in Pebble-Bed High-Temperature Gas-Cooled Reactor

更新时间：2025-07-28

- 3D Numerical Simulation on Bypass Flow in Pebble-Bed High-Temperature Gas-Cooled Reactor
- Vol. 58, Issue 8, Pages: 156-165(2024)
- 作者机构：
  
  1. 华能核能技术研究院有限公司,上海,200126
  2. 西安交通大学热流科学与工程教育部重点实验室,西安,710049
- 作者简介：
- 基金信息：
- DOI：10.7652/xjtuxb202408016
  CLC： TL334
- Online First：10 August 2024，
  
  Published：2024
- 稿件说明：
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LIU Wei, SHI Jin, SHAO Jikai, et al. 3D Numerical Simulation on Bypass Flow in Pebble-Bed High-Temperature Gas-Cooled Reactor[J]. 2024, 58(8): 156-165.
DOI：

LIU Wei, SHI Jin, SHAO Jikai, et al. 3D Numerical Simulation on Bypass Flow in Pebble-Bed High-Temperature Gas-Cooled Reactor[J]. 2024, 58(8): 156-165. DOI： 10.7652/xjtuxb202408016.

摘要

针对球床式高温气冷堆中散体布置的石墨砖等结构带来的旁流问题

数值模拟了高温气冷堆满功率稳态运行时卸料管、控制棒通道及窄缝中的旁流特征。通过结合华能集团自主研发的HN-750型球床式高温气冷堆的结构特点和流道特征

建立了包含窄缝、顶反射层、堆芯球床、底反射层及底部球腔的反应堆三维几何模型和近真实物理数学模型

生成了网格数为2.6亿的混合网格。结果表明

总旁流占总流量比例为29.25%

窄缝旁流占总流量比例为24.43%

并且呈现出回流特性

卸料管旁流占比3.87%

控制棒通道旁流占比0.95%。该研究考虑了非轴对称的进出口结构

是对现有的球床式高温气冷堆二维轴对称模型的补充和提升; 该研究针对球床式高温气冷堆的大规模三维数值计算

为球床式高温气冷堆的热工水力优化和安全分析提供了丰富的数据支撑。

Abstract

The bypass flow characteristics in such structures as graphite brick arranged in the pebble-bed high-temperature gas-cooled reactor(HTGR)during full-power steady-state operation is numerically simulated. In view of the structural features and flow characteristics of the HN-750 pebble-bed HTGR developed independently by Huaneng Group

a three-dimensional geometric model of the reactor including narrow gaps

top reflector layer

core pebble bed

bottom reflector layer

and bottom pebble cavity

along with a physically realistic mathematical model

is established. A hybrid grid with a mesh count of 260 million is generated. The results indicate that the total bypass flow accounts for 29.25% of the total flow rate

with narrow gap bypass flow with reflux characteristics occupying 24.43%

discharge pipe bypass flow occupying 3.87%

and control rod channel bypass flow occupying 0.95%. The non-axisymmetric inlet and outlet structures are considered in this research

serving as a complement and enhancement to the existing two-dimensional axisymmetric models of pebble-bed HTGR. Large-scale three-dimensional numerical calculations for pebble-bed HTGRs are represented

with abundant data support being provided for the thermal-hydraulic optimization and safety analysis of pebble-bed HTGRs.

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references

张浩, 王建建. 模块式高温气冷堆的技术背景及展望 [J]. 中国核电, 2021, 14(3): 419-422.

ZHANG Hao, WANG Jianjian. The technical base and development prospects of the modular high temperature gas cooled reactor [J]. China Nuclear Power, 2021, 14(3): 419-422.

张成龙, 袁媛, 刘国明, 等. 棱柱式超级安全气冷堆堆芯物理特性研究 [J]. 原子能科学技术, 2023, 57(1): 156-164.

ZHANG Chenglong, YUAN Yuan, LIU Guoming, et al. Research on core physical characteristics of prismatic super-safe gas-cooled reactor [J]. Atomic Energy Science and Technology, 2023, 57(1): 156-164.

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, 20(3): 211-219.

WU Zongxin, ZHANG Zuoyi. World development of nuclear power system and high temperature gas-cooled reactor [J]. Chinese Journal of Nuclear Science and Engineering, 2000, 20(3): 211-219.

XU Yuanhui, ZUO Kaifen. Overview of the 10 MW high temperature gas cooled reactor: test module project [J]. Nuclear Engineering and Design, 2002, 218(1/2/3): 13-23.

ZHANG Zuoyi, WU Zongxin, WANG Dazhong, et al. Current status and technical description of Chinese 2×250 MWth HTR-PM demonstration plant [J]. Nuclear Engineering and Design, 2009, 239(7): 1212-1219.

ZHENG Yanhua, CHEN Fubing, SHI Lei. Analysis of bypass effect on a 250 MW high temperature gas-cooled reactor [C]//2014 22nd International Conference on Nuclear Engineering. New York, NY, USA: ASME, 2014: V003T06A002.

SMITH B L. Assessment of CFD codes used in nuclear reactor safety simulations [J]. Nuclear Engineering and Technology, 2010, 42(4): 339-364.

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.

LI Linsen, WANG Kan, SONG Xiaoming. International research progress of CFD application in analysis of nuclear power system [J]. Nuclear Power Engineering, 2009, 30(S1): 28-33.

SUN Ximing, CHEN Zhipeng, SUN Jun, et al. CFD investigation of bypass flow in HTR-PM [J]. Nuclear Engineering and Design, 2018, 329: 147-155.

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): 39-45.

SONG Shixiong, WEI Quan, CAI Xiangzhou, et al. High temperature gas-cooled pebble bed reactor steady state thermal-hydraulics analyses based on CFD method [J]. Nuclear Techniques, 2013, 36(12): 39-45.

孙世妍, 张佑杰, 郑艳华, 等. 高温气冷堆热工分析模型改进与堆芯温度场分析 [J]. 原子能科学技术, 2021, 55(8): 1376-1385.

SUN Shiyan, ZHANG Youjie, ZHENG Yanhua, et al. Improvement of thermal hydraulic model and analysis of core temperature distribution of high temperature gas-cooled reactor [J]. Atomic Energy Science and Technology, 2021, 55(8): 1376-1385.

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.

PENG Haoran, SUN Jun. Investigation of flow and heat transfer in the pebble bed of the high temperature gas-cooled reactor [J]. Journal of Engineering Thermophysics, 2016, 37(5): 1076-1083.

孙世妍, 张佑杰, 郑艳华, 等. HTR-10超高温运行堆芯温度场分析 [J]. 清华大学学报(自然科学版), 2021, 61(11): 1301-1307.

SUN Shiyan, ZHANG Youjie, ZHENG Yanhua, et al. Core temperature distributions in HTR-10 operating at very high temperatures [J]. Journal of Tsinghua University(Science and Technology), 2021, 61(11): 1301-1307.

张双宝, 李良星, 谢伟, 等. 球床式高温气冷堆堆芯三维建模及稳态热工水力分析 [J]. 中国科学院大学学报, 2020, 37(2): 186-191.

ZHANG Shuangbao, LI Liangxing, XIE Wei, et al. 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.

Nuclear Safety Standards Commission. Reactor core design of high-temperature gas-cooled reactors: part 2

heat transfer in spherical fuel elements: KTA 3102.2[S]. Salzgitter, Germany: Nuclear Safety Standards Commission, 1983.

Nuclear Safety Standards Commission. Reactor core design of high-temperature gas-cooled reactors: part 3

loss of pressure through friction in pebble bed cores: KTA 3102.3 [S]. Salzgitter, Germany: Nuclear Safety Standards Commission, 1981.

BECKER S, LAURIEN E. Three-dimensional numerical simulation of flow and heat transport in high-temperature nuclear reactors [J]. Nuclear Engineering and Design, 2003, 222(2/3): 189-201.

郝琛, 李富, 郭炯. 球床式高温气冷堆球流混流的模拟 [J]. 清华大学学报(自然科学版), 2014, 54(5): 624-628.

HAO Chen, LI Fu, GUO Jiong. Simulations of mixing in the pebble flow of a pebble bed HTR [J]. Journal of Tsinghua University(Science and Technology), 2014, 54(5): 624-628.

GAO Zuying, SHI Lei. Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core [J]. Nuclear Engineering and Design, 2002, 218(1/3): 51-64.

Nuclear Safety Standards Commission. Reactor core design for high-temperature gas-cooled reactors: part 1

calculation of the material properties of helium: KTA 3102.1[S]. Salzgitter, Germany: Nuclear Safety Standards Commission, 1978.

RUAN Bo, MENG Hua. Supercritical heat transfer of cryogenic-propellant methane in rectangular engine cooling channels [J]. Journal of Thermophysics and Heat Transfer, 2012, 26(2): 313-321.

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.

PENG Haoran, SUN Jun. Investigation of flow and heat transfer in the pebble bed of the high temperature gas-cooled reactor [J]. Journal of Engineering Thermophysics, 2016, 37(5): 1076-1083.

VAN WYK M. Verification of leakage through the side reflector graphite of the PBMR reactor [D]. Vanderbijlpark, The Republic of South Africa: North-West University, 2004.

RÜTTEN H J, HAAS K A, BROCKMANN H, et al. V.S.O.P.(99/09)computer code system for reactor physics and fuel cycle simulation [M]. Giessen, Germany: Institut für Energieforschung, 2009.

CHEN Fubing, HAN Zihao. Steady-state thermal fluids analysis for the HTR-PM equilibrium core [J]. International Journal of Advanced Nuclear Reactor Design and Technology, 2021, 3: 11-17.

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