摘要
在新燃料组件运输过程中,临界安全是重点。使用MCNP程序对中国先进研究堆新燃料组件的运输进行临界安全计算分析,通过选取最不利临界安全的次临界限值、组件模型参数、事故工况来保证计算结果的保守性。结果表明,运输货包的临界安全指数可确定为0。该结果可为中国先进研究堆(CARR)的新燃料组件运输容器的研发提供参考依据。
In the transportation of fresh fuel assemblies, one of the most important problems that the review department cares about is criticality safety. In this article, the criticality safety analysis on the fuel assembly transportation of China Advanced Research Reactor is taken by MCNP code. The calculation is conservative by ensuring the subcritical limit, model parameters and accidental conditions. As a result, the criticality safety index of the transport package can be determined as 0. The collusion of this article can provide reference to the researching and manufacture of the transport package for CARR fresh fuel assembly.
作者
贾晓淳
JIA Xiaochun(Department of Nuclear Engineering Design,China Institute of Atomic Energy,Beijing 102413,China)
出处
《同位素》
CAS
2022年第6期513-518,I0004,共7页
Journal of Isotopes
关键词
中国先进研究堆
MCNP程序
次临界限值
临界安全分析
临界安全指数
China Advanced Research Reactor
MCNP code
subcritical limit
criticality safety analysis
criticality safety index
