Neutron Distribution in the Nuclear Fuel Cell using Collision Probability Method with Quadratic Flux Approach
Author:
Publisher
IOP Publishing
Subject
General Medicine
Link
http://stacks.iop.org/1757-899X/180/i=1/a=012040/pdf
Reference10 articles.
1. A three-dimensional collision probability method: Criticality and neutron flux in a hexahedron setup
2. Neutron Flux Interpolation with Finite Element Method in the Nuclear Fuel Cell Calculation using Collision Probability Method
3. Nuclear Fuel Cell Calculation Using Collision Probability Method with Linear Non Flat Flux Approach
Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Study of Neutronic Performance of Sodium-Cooled Fast Reactor Design for Various Output Power Using Radial Fuel Shuffling Strategy;Journal of Physics: Conference Series;2021-06-01
2. The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method;MATEC Web of Conferences;2018
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