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Volume 34 Issue 1
Mar.  2025
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XING Shuo, YAO Dong, YIN Chun-yu, PANG Hua, TU Xiao-lan. Preliminary Study on SCWR Fuel Rod Performance Analysis Code[J]. Nuclear Power Engineering, 2013, 34(1): 97-100,120.
Citation: XING Shuo, YAO Dong, YIN Chun-yu, PANG Hua, TU Xiao-lan. Preliminary Study on SCWR Fuel Rod Performance Analysis Code[J]. Nuclear Power Engineering, 2013, 34(1): 97-100,120.

Preliminary Study on SCWR Fuel Rod Performance Analysis Code

  • Received Date: 2012-10-17
  • Rev Recd Date: 2012-11-19
  • Available Online: 2025-03-08
  • A SCWR fuel rod performance analysis code is developed in this paper,based on a PWR fuel rod performance analysis code,by analyzing its model and calculation method.The new code is developed on the basis of intensive analyses of SCWR characteristics,focused on the coolant-fuel rod outside surface heat transfer and cladding properties model.Lastly,the performance analysis code was successfully tested on fuel rod of 1/8 HPLWR fuel assembly,then the paper compares the results with that from the sub-channel analysis code ATHAS,which shows that the error is small.

     

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