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Transmission Probability Method for Calculation of Neutron Flux Distributions in Hexagonal Geometry

机译：六角几何中子通量分布计算的传输概率法

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摘要

A transmission probability method implemented in the program TPHEX is described. This program was developed for the calculation of neutron flux distributions in hexagonal light water reactor fuel assemblies. The accuracy appears to be superior to diffusion theory, and the computation time is shorter than that of the collision probability method. (Atomindex citation 11:562515)

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作者
Wasastjerna, F.; Lux, I.;
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年度 1980
页码 p.1-138
总页数 138
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Computer codes; Fuel assemblies; Wwer type reactors; Computer calculations; Distribution; Flux density; Hexagonal configuration; Neutron flux; Probability; Reactor lattices; T codes; Transmission;

机译：计算机规范;燃料组件; Wwer型反应堆;计算机计算;分布;通量密度;六角形配置;中子通量;概率;反应堆晶格; T代码;传输;

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1. The P _ij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method [J] . Mohammad Ali Shafii, Jakaria Usman, Seni H. J. Tongkukut, MATEC Web of Conferences . 2018,第12期

机译：碰撞概率法计算核燃料电池平板几何中一维中子输运的 P _{ij 矩阵和通量}
2. DEVELOPMENT OF A COMPUTER CODE FOR NEUTRONIC CALCULATIONS OF A HEXAGONAL LATTICE OF NUCLEAR REACTOR USING THE FLUX EXPANSION NODAL METHOD [J] . Mohammadnia Meysam, Pazirandeh Ali, Sedighi Mostafa Nuclear technology & radiation protection . 2013,第3期

机译：磁通膨胀结节法开发核反应堆六角格中性计算的计算机代码
3. Development of a computer code for neutronic calculations of a hexagonal lattice of nuclear reactor using the flux expansion nodal method [J] . Mohammadnia Meysam, Pazirandeh Ali, Sedighi Mostafa Nuclear technology & radiation protection . 2013,第3期

机译：使用通量膨胀节法开发用于中子计算核反应堆六边形晶格的计算机代码
4. The P_(ij) matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method [C] . Mohammad Ali Shafii, Jakaria Usman, Seni H. J. Tongkukut, Applied Sciences and Engineering Conference . 2018

机译：采用碰撞概率法测定核燃料电池板几何形状中一维中子输送的P_（IJ）矩阵和磁通量
5. Newton-Krylov methods for the solution of the k-eigenvalue problem in multigroup neutronics calculations. [D] . Gill, Daniel F. 2009

机译：用于多组中子学计算中k特征值问题的Newton-Krylov方法。
6. The discrete ordinate method for angular flux calculations in slab geometry [O] . M. Lahdour, T. El Bardouni, M. Mohammed, 2019

机译：平板几何中角通量的离散纵坐标法
7. The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method [O] . Mohammad Ali Shafii, Jakaria Usman, Seni H. J. Tongkukut, 2018

机译：采用碰撞概率法测定核燃料电池板几何中一维中子输送的PIJ矩阵和磁通计
8. Fast Computation of the Neutron Flux Distribution in X-Y Geometry Using the QP0 First Collision Probability Method [R] . Stepanek, J., Hager, H. 1978

机译：利用Qp0第一碰撞概率方法快速计算X-Y几何中子通量分布

Transmission Probability Method for Calculation of Neutron Flux Distributions in Hexagonal Geometry

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