Progress in nodal methods for the solution of the neutron diffusion and transport equations
- 1 January 1986
- journal article
- Published by Elsevier in Progress in Nuclear Energy
- Vol. 17 (3) , 271-301
- https://doi.org/10.1016/0149-1970(86)90034-x
Abstract
No abstract availableKeywords
This publication has 23 references indexed in Scilit:
- Assembly homogenization techniques for light water reactor analysisProgress in Nuclear Energy, 1986
- An Efficient Algorithm for Nodal-Transport Solutions in Multidimensional GeometryNuclear Science and Engineering, 1985
- A Review of Neutron Transport ApproximationsNuclear Science and Engineering, 1982
- Angular current approximations in neutron transport calculations using interface currents—A reviewProgress in Nuclear Energy, 1981
- Nodal methods for three-dimensional simulatorsProgress in Nuclear Energy, 1981
- Effective one-group coarse-mesh method for calculating three-dimensional power distribution in fast reactorsAnnals of Nuclear Energy, 1979
- Optimized Iteration Strategies and Data Management Considerations for Fast Reactor Finite Difference Diffusion Theory CodesNuclear Science and Engineering, 1977
- Diffusion Synthetic Acceleration Methods for the Diamond-Differenced Discrete-Ordinates EquationsNuclear Science and Engineering, 1977
- Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor CoresNuclear Science and Engineering, 1977
- Multichannel Flux SynthesisNuclear Science and Engineering, 1962