Stochastic neutron transport equations for rod and plane geometries
- 31 January 2000
- journal article
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 27 (2) , 99-116
- https://doi.org/10.1016/s0306-4549(99)00055-9
Abstract
No abstract availableKeywords
This publication has 9 references indexed in Scilit:
- Real and virtual sampling in variational processing of stochastic simulation in neutron transport: The one-dimensional rodAnnals of Nuclear Energy, 1998
- On the use of Monte Carlo perturbation in neutron transport problemsAnnals of Nuclear Energy, 1998
- Neutron Cross-Section Probability Tables in TRIPOLI-3 Monte Carlo Transport CodeNuclear Science and Engineering, 1998
- Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron FluenceNuclear Technology, 1996
- A Stochastic Cellular Automata Model for Neutron TransportNuclear Science and Engineering, 1993
- On the Convergence of Finite-Differenced Multigroup, Discrete-Ordinates Methods for Anisotropically Scattered Slab MediaSIAM Journal on Numerical Analysis, 1989
- Theoretical Properties of One-Dimensional Discrete OrdinatesSIAM Journal on Numerical Analysis, 1979
- Linear stochastic neutron transport theoryProceedings of the Royal Society of London. Series A. Mathematical and Physical Sciences, 1978
- Convergence of the Discrete-Ordinates Method for Anisotropically Scattering Multiplying Particles in a Subcritical SlabSIAM Journal on Numerical Analysis, 1973