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微型中子源核反应堆绝对中子通量密度计算
Calculation of absolute thermal neutron flux density in the core of miniature neutron source reactor
【摘要】 阐述微型中子源核反应堆绝对中子通量密度测量的数值算法机理,并给出其计算公式.结合深圳大学微堆实例给出计算结果,与实际中子通量密度对比,说明应用该方法时的注意事项.
【Abstract】 Numerical analysis about the measurement of absolute thermal neutron flux density in the core of Miniature Neutron Source Reactor ( MNSR) was illustrated in detail. The calculation formula was deduced, and the program frame was provided. The algorithm was applied to measure the flux density of Shenzhen University MNSR, and the result was compared with actual neutron flux density. At last, some points of attention were mentioned.
【基金】 国家自然科学基金资助项目(10275074)广东省自然科学基金资助项目(011742)深圳大学科研基金资助项目(200113)
- 【文献出处】 深圳大学学报 ,Shenzhen University Journal , 编辑部邮箱 ,2004年02期
- 【分类号】TL375.4
- 【被引频次】3
- 【下载频次】179