Improvement of Thermal Hydraulic Model and Analysis of Core Temperature Distribution of High Temperature Gas-cooled Reactor

被引：0

作者：

Sun S. ^{[1
,2
]}

Zhang Y. ^{[1
]}

Zheng Y. ^{[1
]}

Xia B. ^{[1
]}

机构：

[1] Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing

[2] China Institute of Nuclear Industry Strategy, Beijing

来源：

Zhang, Youjie | 1600年 / Atomic Energy Press卷 / 55期

关键词：

Core temperature distribution; HTR-10; Model improvement; Pebble-bed high temperature gas-cooled reactor; Safety analysis; Thermal hydraulic simulation;

D O I：

10.7538/yzk.2020.youxian.0354

中图分类号：

学科分类号：

摘要：

How to simulate the core temperature distribution more accurately is one of the key issues in the safety analysis of the pebble-bed high temperature gas-cooled reactor, especially in the study of very-high-temperature reactor operation. Due to the uncertainty of the pebble flow in the core, and the structural materials such as graphite blocks and carbon bricks assembled in bulk, the coolant flow paths in the reactor are complicated, which cause difficulties for accurate thermal hydraulic simulations, which can be further optimized. Based on the structure and flow path characteristics of HTR-10, the heat transfer process was briefly analyzed, which illustrates the importance of accurately repartitioning the areas of structural components and coolant flow paths in the thermal hydraulic simulation to obtain a more accurate core temperature distribution. After the flow paths were analyzed in detail, the original thermal hydraulic model for HTR-10 established in the THERMIX code was improved, simulating the bypass flow of core coolant more reasonably, and describing the core coolant flow and heat transfer process more accurately. Compared with the experimental results, the improved model significantly improves the simulating accuracy of the temperature distribution of the peripheral components of the pebble bed. The results also show that the maximum temperature of both the fuel and the graphite reflectors does not exceed the heat resistance limit of the material when the reactor is operating at full power and steady state under the rated design condition. © 2021, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：1376 / 1385

页数：9

共 16 条

[1] WANG Jie, Preliminary study on technical base and future potential of high temperature gas-cooled reactor, Chinese Journal of Nuclear Science and Engineering, 22, 4, pp. 325-330, (2002)
[2] A technology roadmap for Generation Ⅳ Nuclear Energy Systems, Philosophical Review, 66, 2, pp. 239-241, (2002)
[3] GAO Zuying, SHI Lei, Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core, Nuclear Engineering and Design, 218, 1, pp. 51-64, (2002)
[4] (2009)
[5] CHEN Zhipeng, SUN Ximing, SUN Jun, Investigation of the bypass flow in vertical narrow gaps of reflectors in the high temperature gas-cooled reactor, Journal of Engineering Thermophysics, 39, 3, pp. 592-597, (2018)
[6] WU Zongxin, LIN Dengcai, ZHONG Daxin, The design features of the HTR-10, Nuclear Engineering and Design, 218, 1, pp. 25-32, (2002)
[7] ZHENG Yanhua, CHEN Fubing, SHI Lei, Analysis of bypass effect on a 250 MW high temperature gas cooled reactor, Proceedings of the 2014 22nd International Conference on Nuclear Engineering, (2014)
[8] (2009)
[9] CLEVELAND J C, GREENE S R., Application of THERMIX-KONVEK code to accident analyses of modular pebble bed high temperature reactors (HTRs), (1986)
[10] SHI Lei, LIU Haibin, YANG Xiaojing, Et al., A personal computer-based simulation-and-control-integrated platform for 10-MW High-temperature Gas-cooled Reactor, Nuclear Technology, 145, 2, pp. 189-203, (2004)

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