Numerical Caseology by Lagrange Interpolation for the 1D Neutron Transport Equation in a Slab
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 1-13
Technical Paper / dx.doi.org/10.1080/00295639.2022.2097494
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 14-24
Technical Paper / dx.doi.org/10.1080/00295639.2022.2103344
Post-Neutron Fission Product Yield Distribution in the Spontaneous Fission of 244Cm
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 25-44
Technical Paper / dx.doi.org/10.1080/00295639.2022.2103345
An Analysis of Transport Effects in Steady-State Simulation of the Molten Salt Reactor Experiment
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 45-73
Technical Paper / dx.doi.org/10.1080/00295639.2022.2097565
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 74-91
Technical Paper / dx.doi.org/10.1080/00295639.2022.2102391
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 92-103
Technical Paper / dx.doi.org/10.1080/00295639.2022.2102392
Infiltration and Evaporation in Multiplying Porous Media and Associated Criticality Phenomena
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 104-131
Technical Paper / dx.doi.org/10.1080/00295639.2022.2103336
Nuclear Science and Engineering / Volume 197 / Number 1 / January 2023 / Pages 132-143
Technical Paper / dx.doi.org/10.1080/00295639.2022.2103338