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tandfonline.com/action/journalInformation?journalCode=tnst20 Journal of Nuclear Science and Technology ISSN: 0022-3131 (Print) 1881-1248 (Online) Journal homepage: https://www.tandfonline.com/loi/tnst20 Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation Fubing CHEN , Yujie DONG , Yanhua ZHENG , Lei SHI &

Zuoyi ZHANG To cite this article: Fubing CHEN , Yujie DONG , Yanhua ZHENG , Lei SHI &

Zuoyi ZHANG (2009) Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation, Journal of Nuclear Science and Technology, 46:6, 572-580, DOI: 10.1080/18811248.2007.9711564 To link to this article: https://doi.org/10.1080/18811248.2007.9711564 Published online:

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3 View citing articles Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation Fubing CHEN? , Yujie DONG, Yanhua ZHENG, Lei SHI and Zuoyi ZHANG Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China (Received October 20,

2008 and accepted in revised form February 25, 2009) Within the framework of a Coordinated Research Project on Evaluation of High Temperature Gas- Cooled Reactor Performance (CRP-5) initiated by the International Atomic Energy Agency (IAEA), the calculation of steady-state temperature distribution of the

10 MW High Temperature Gas-Cooled Reactor- Test Module (HTR-10) under its initial full power experimental operation has been de?ned as one of the benchmark problems. This paper gives the investigation results obtained by di?erent countries who participate in solving this benchmark problem. The validation works of the THERMIX code used by the Institute of Nuclear and New Energy Technology (INET) are also presented. For the benchmark items de?ned in this CRP, various calculation results correspond well with each other and basically agree the experimental results. Discrepancies existing among various code results are preliminarily attributed to di?erent methods, models, material properties, and so on used in the computations. Temperatures calculated by THERMIX for the measuring points in the reactor internals agree well with the experimental values. The maximum fuel center temperatures calculated by the participants are much lower than the limited value of 1,230 C. According to the comparison results of code-to-code as well as code-to- experiment, THERMIX is considered to reproduce relatively satisfactory results for the CRP-5 benchmark problem. KEYWORDS: Coordinated Research Project on Evaluation of High Temperature Gas-Cooled Reactor Performance (CRP-5),

10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10), steady-state temperature distribution, code-to-code, code-to-experiment, benchmark cal- culation, THERMIX I. Introduction The

10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10), designed, constructed and operated by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, is a major project in the energy sector of the National High Technology Research and De- velopment Program of China1) (also known as the

863 Pro- gram). As a graphite-moderated and helium-cooled pebble bed reactor, the HTR-10 represents main design features and safety characteristics of the HTR-Module,2) which is a con- cept of the modular High Temperature Gas-Cooled Reactor (HTGR) originally proposed and developed in Germany. The reactor and steam generator are housed in two separate steel pressure vessels, which are arranged side by side and connected to each other by a horizontal hot gas duct pressure vessel. These three vessels make up of the primary pressure boundary of the HTR-10 and are in touch with the cold helium coming from the helium circulator. The detailed structures of the reactor are described in Sec. II. As the ?rst HTGR in China, the HTR-10 attained its ?rst criticality on Dec. 1, 2000. Afterwards, a series of commissioning tests were done for the reactor system and other key components at a low power. At 19:30 Jan. 26, 2003, the HTR-10 achiev- ed the full power operation ?rstly. Then the reactor ran continuously for