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	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
	2010-10-12 ; 2010-10-12
关键词	Practical Theoretical or Mathematical Experimental/ fission reactor design fission reactor fuel fission reactor operation fission reactor theory gas cooled reactors nuclear engineering computing/ benchmark calculation steady-state temperature distribution HTR-10 power operation CRP-5 benchmark International Atomic Energy Agency high temperature gas-cooled reactor-test module THERMIX code Institute of Nuclear and New Energy Technology INET THERMIX reactor fuel reactor design/ A2841E Fission reactor theory and physics A2841D Fission reactor design A2842D Fission reactor fuel elements A2850I Gas cooled reactors A2843 Fission reactor operation A2841C Computing for fission reactor theory and design B8220B Nuclear reactors C7470 Nuclear engineering computing
中文摘要	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 defined as one of the benchmark problems. This paper gives the investigation results obtained by different 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 defined 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 different 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 degrees 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.
语种	英语
出版者	Atomic Energy Society of Japan ; Japan
内容类型	期刊论文
源URL	[http://hdl.handle.net/123456789/79333]
专题	清华大学
推荐引用方式 GB/T 7714	Fubing Chen,Yujie Dong,Yanhua Zheng,et al. Benchmark calculation for the steady-state temperature distribution of the HTR-10 under full-power operation[J],2010, 2010.
APA	Fubing Chen,Yujie Dong,Yanhua Zheng,Lei Shi,&Zuoyi Zhang.(2010).Benchmark calculation for the steady-state temperature distribution of the HTR-10 under full-power operation..
MLA	Fubing Chen,et al."Benchmark calculation for the steady-state temperature distribution of the HTR-10 under full-power operation".(2010).

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