PT-SCWR燃料组件的物理热工耦合分析

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

1. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China;
2. China Nuclear Power Technology Research Institute, Shenzhen, 518026, China

摘要: 利用蒙特卡罗程序(MCNP)和子通道程序ATHAS对压力管式超临界水堆(PT-SCWR)燃料组件进行物理热工耦合分析;这种耦合方式是合理有效的。分析结果表明:PT-SCWR组件中燃料富集度的分布对燃料组件的径向功率分布有很大影响,通过调节各圈棒束的燃料富集度,可以有效地改善径向功率分布;慢化剂厚度对棒束轴向功率分布有明显影响,当慢化剂厚度为25 cm时,轴向功率分布最接近余弦形状。
- PT-SCWR /
- 物理-热工耦合分析 /
- MCNP /
- 子通道程序ATHAS
Abstract: 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.
- PT-SCWR /
- Coupled analysis /
- MCNP /
- Sub-channel code ATHAS