文章基本信息

标题：The P ij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method
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作者：Mohammad Ali Shafii ; Jakaria Usman ; Seni H. J. Tongkukut 等
期刊名称：MATEC Web of Conferences
电子版ISSN：2261-236X
出版年度：2018
卷号：197
DOI：10.1051/matecconf/201819702006
语种：English
出版社：EDP Sciences
摘要：Calculation of Pijmatrix of one-dimensional neutron transport in the slab geometry of the nuclear fuel cell using Collision Probability (CP) method has been done. Pijmatrix is one of important parameters within the distribution of neutron flux in the nuclear fuel cell. The CP method is the most efficient methods to solve the neutron transport equation in the reactor core. The study is focused on neutron interaction with nuclear fuel cell of U-235 and U-238 for homogeneous condition. The parameters to calculate the Pijmatrix are the cross section of nuclear fuel, width of the region and number of regions. A lattice of slabs have been constructed using void boundary conditions for model of finite system to calculate the collision probabilities. If the Pijmatrix has been calculated then neutron flux can be determined. The results show that total value of Pijmatrix using CP method for U-235 and U-238 is less than one, respectively. This is in accordance with the definition of void boundary conditions for finite slab geometry. Along with Pijmatrix, neutron flux is also appropriate with the reference.