
基于MCNP和ORIGEN2耦合程序的IHNI-1型堆裂变产物中毒及燃耗分析
The fission product poisoning and burnup calculation for IHNI-1 reactor based on coupled codeof MCNP-ORIGEN
Zhang Xinyi1、Zhao Zhumin1、Jiang Xinbiao1、Guo Hewei1、Chen Lixin1、Zhou Yongmao2
为了准确地计算反应堆的裂变产物中毒和燃耗问题,开发了一套蒙特卡罗方法程序系统。利用通用的燃耗计算方法,基于MCNP和ORIGEN2,编写了相关的数据转换、截面修正、数据接口程序,实现了MCNP和ORIGEN2程序的耦合。采用堆芯精细结构划分,对医院中子照射器I型堆裂变产物中毒和燃耗进行了计算分析。
To calculate the fission product poisoning and burnup of the reactor accurately, the paper sets up the coupled calculation methods based on MCNP code and ORIGEN2 code and program data translation, cross section revision and date interface codes. Making use of elaborate reactor model to calculate the fission product poisoning and burnup for in-hospital neutron irradiator mark 1 reactor.
IHNI-1 / MCNP / ORIGEN2 / burnup
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