主产裂变<sup>99</sup>Mo的研究堆初步热工安全设计

主产裂变⁹⁹Mo的研究堆初步热工安全设计

摘要: 针对主产裂变⁹⁹Mo的研究堆的需求，设计了堆芯总体方案。根据中子物理计算功率分布和该反应堆的热工水力设计限值，应用COTH程序确定了反应堆的热工水力设计参数。通过结果分析可知，该堆芯设计方案可满足设计要求。

Abstract: The reactor core general design of the research reactor mainly for production of fission ⁹⁹Mo was developed. The reactor’s thermal hydraulic parameters were calculated by using the COTH code based on the neutronics calculation result and the thermal hydraulic design limitation. The results show that the core general design satisfies the design requirement.