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Volume 34 Issue 6
Mar.  2025
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LIU Wei, BAI Ning, DAN Jian-qiang, ZHU Yuan-bing, ZHANG Bo, LI Jing-gang. Coupled Neutronics/Thermal-Hydraulics Analysis of PT-SCWR Fuel Assembly[J]. Nuclear Power Engineering, 2013, 34(6): 5-9.
Citation: LIU Wei, BAI Ning, DAN Jian-qiang, ZHU Yuan-bing, ZHANG Bo, LI Jing-gang. Coupled Neutronics/Thermal-Hydraulics Analysis of PT-SCWR Fuel Assembly[J]. Nuclear Power Engineering, 2013, 34(6): 5-9.

Coupled Neutronics/Thermal-Hydraulics Analysis of PT-SCWR Fuel Assembly

  • Received Date: 2012-09-28
  • Rev Recd Date: 2013-10-08
  • Available Online: 2025-03-08
  • The neutronics code Monte Carlo N-Particle code(MCNP) and the sub-channel analysis code Advanced Thermal-Hydraulics Analysis Sub-channel(ATHAS) are used in a coupled way to better understand the design characteristics of PT-SCWR fuel assembly. The developed coupled code is reasonable and effective. The results show that: The distribution of PT-SCWR fuel enrichment has strong effect on radial power distribution. It is available to flatten the radial power distribution by changing the fuel enrichment of the inner and outer fuel rods. Moderator thickness has strong effect on the axial power distribution: when it is 25 cm, the axial power distribution approaches a cosine configuration.

     

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