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Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code

[+] Author Affiliations
Xiaoyan Wei, Xin Jin, Yongjun Deng, Guoliang Zhang, Xiangang Fu

China Nuclear Power Technology Research Institute, ShenZhen, China

Paper No. ICONE25-67144, pp. V003T02A043; 6 pages
  • 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
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5781-6
  • Copyright © 2017 by ASME


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.

Copyright © 2017 by ASME
Topics: Modeling , Fuel rods



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