| 轻水反应堆燃料组件中子通量和功率分布的计算程序 |
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| 引用本文： | 谢仲生,章宗耀.轻水反应堆燃料组件中子通量和功率分布的计算程序[J].核动力工程,1989,10(3):1-6,12. |
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| 作者姓名： | 谢仲生 章宗耀 |
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| 作者单位： | 西安交通大学
(谢仲生，尹邦华)，西南反应堆工程研究设计院(章宗耀) |
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| 摘 要： | 本文介绍用穿透几率法计算二维轻水堆燃料组件内中子通量分布的两种计算模型和程序.在子区内及表面上中子通量采用线性空间分布近似,子区表面上角通量分别采用准 DP_1和 QP_1近似。对一些轻水堆组件基准问题作了验证计算。计算结果与 S_N、节块 S_N 以及积分输运理论等方法进行比较,其结果符合良好。这些程序可用于轻水堆燃料组件的计算。
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| 关 键 词： | 轻水堆 燃料组件 中子通量 功率 |
Two-Dimensional Neutron Flux Calculation Codes for Fuel Assembly of Light Water Reactor |
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| Xie Zhongsheng,Yin Banghua.Two-Dimensional Neutron Flux Calculation Codes for Fuel Assembly of Light Water Reactor[J].Nuclear Power Engineering,1989,10(3):1-6,12. |
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| Authors: | Xie Zhongsheng Yin Banghua |
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| Abstract: | Two multigroup transport assembly codes for light water reactor are dev-eloped in this paper.The interior flux within a mesh is assumed to be line-arly dependent on X and Y coordinates.At the mesh surfases the linear space distribution and the quasi-2P_1 and Qp_1 approximations for the anisotropic angular distribution are considered.A series of 2-D assembly benchmark pro-blems of LWR have been tested.The numerical results are in good agreement with those of S_N,discrete nodal transport,surface flux transport and collision probability methods.These codes can be successfully used in the design of LWR assembly. |
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| Keywords: | Fuel assembly Neutron transport equation Transmission probability |
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