2012, Volume 14, Issue 8
Strategic Study of CAE >> 2012, Volume 14, Issue 8
The burnup calculation for in-hospital neutron irradiator mark 1 reactor based on coupled code of WIMS and MCNP
1. Northwest Institute of Nuclear Technology, Xi'an 710024, China;
2. China Zhongyuan Engineering Corporation, China National Nuclear Corporation, Beijing 100191, China
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Abstract
The paper set up the coupled calculation methods of criticality and burnup based on WIMS code and MCNP code, and validated the method. Through the calculation results of cells and the comparison of burnup experiments of Xi’an pulsed reactor, the validity and rationality of the coupled code were proved. The article utilized the coupled code to compute and analyze the burnup of in hospital neutron irradiator mark 1(IHNI-1) reactor at last.
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References
[ 1 ] 谢仲生，邓力．中子输运理论数值计算方法［Ｍ］．西安：西北工业大学出版社，２００５：４８－５４．
[ 2 ] 李树．堆芯燃耗分析系统及其应用［Ｄ］．西安：西安交通大学核能与热能工程系，２０００．
[ 3 ] 张文首，阿景烨，陈达，等．西安脉冲堆燃料元件燃耗无损实验测量［Ｊ］．核动力工程，２００９，３０（３）：３０－３４． link1
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