JASMINE is a computer program for the comprehensive performance analysis of fuel rods in nuclear reactors and was developed at China General Nuclear Power Cooperation (CGNPC). The JASMINE code, which is built around a quasi-two-dimensional analysis of fuel rod, consists of a clearly defined mechanical/mathematical framework into which physical models can easily be incorporated. In convenience, the important inputs and principal outputs could be shown directly from the interface due to the special platform in the code. During its development great effort was spent on obtaining an extremely flexible platform which is easy to handle, exhibiting much faster running speed for the code. In recent years, much more experiment data is used for the validation to confirm its correctness.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5781-6
PROCEEDINGS PAPER
Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code
Xiaoyan Wei,
Xiaoyan Wei
China Nuclear Power Technology Research Institute, ShenZhen, China
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Xin Jin,
Xin Jin
China Nuclear Power Technology Research Institute, ShenZhen, China
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Yongjun Deng,
Yongjun Deng
China Nuclear Power Technology Research Institute, ShenZhen, China
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Guoliang Zhang,
Guoliang Zhang
China Nuclear Power Technology Research Institute, ShenZhen, China
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Xiangang Fu
Xiangang Fu
China Nuclear Power Technology Research Institute, ShenZhen, China
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Xiaoyan Wei
China Nuclear Power Technology Research Institute, ShenZhen, China
Xin Jin
China Nuclear Power Technology Research Institute, ShenZhen, China
Yongjun Deng
China Nuclear Power Technology Research Institute, ShenZhen, China
Guoliang Zhang
China Nuclear Power Technology Research Institute, ShenZhen, China
Xiangang Fu
China Nuclear Power Technology Research Institute, ShenZhen, China
Paper No:
ICONE25-67144, V003T02A043; 6 pages
Published Online:
October 17, 2017
Citation
Wei, X, Jin, X, Deng, Y, Zhang, G, & Fu, X. "Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application. Shanghai, China. July 2–6, 2017. V003T02A043. ASME. https://doi.org/10.1115/ICONE25-67144
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