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Volume 25 Issue 6
Dec.  2004
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HUO Xiao-dong, XIE Zhong-sheng. Coupling of Neutronics and Thermal-Hydraulic of CANDU Fuel Management Program and Modification of Time-averaged Model[J]. Nuclear Power Engineering, 2004, 25(6): 481-484,504.
Citation: HUO Xiao-dong, XIE Zhong-sheng. Coupling of Neutronics and Thermal-Hydraulic of CANDU Fuel Management Program and Modification of Time-averaged Model[J]. Nuclear Power Engineering, 2004, 25(6): 481-484,504.

Coupling of Neutronics and Thermal-Hydraulic of CANDU Fuel Management Program and Modification of Time-averaged Model

  • Received Date: 2003-10-15
  • Rev Recd Date: 2004-06-04
  • In this paper, a nonlinear iteration semi-analytic nodal method to solve the diffusion equation and a steady-state single channel thermal-hydraulic code are developed and integrated in the package FMPHWR to realize the coupling of neutronics and thermal-hydraulic. Based on the experiences from PWR, a similar cross-section parameterized method to be used in CANDU is proposed to consider the feedbacks of local parameters. A modified time-averaged model is proposed on the basis of the traditional one. The numerical results show that FMPHWR has superior computational accuracy.

     

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