Volume 101
Number 3
Vectorized and Multitasked Solution of the Few-Group Neutron Diffusion Equations
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 205-216
Technical Paper / dx.doi.org/10.13182/NSE89-A23609
A Transport Method for Treating Three-Dimensional Lattices of Heterogeneous Cells
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 217-225
Technical Paper / dx.doi.org/10.13182/NSE101-217
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 226-242
Technical Paper / dx.doi.org/10.13182/NSE89-A23611
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 243-258
Technical Paper / dx.doi.org/10.13182/NSE89-A23612
Modeling of an Aerosol in Coupled Chambers
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 259-268
Technical Paper / dx.doi.org/10.13182/NSE89-A23613
Role of Spatial Inhomogeneities in Source Term Aerosol Dynamics
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 269-279
Technical Paper / dx.doi.org/10.13182/NSE101-269
Fission-Fragment Energy Deposition in Argon
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 280-284
Technical Paper / dx.doi.org/10.13182/NSE89-A23615
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 285-292
Technical Paper / dx.doi.org/10.13182/NSE89-A23616
Measurement of the Thermal Neutron Induced Fission Cross Section of 243Am
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 293-297
Technical Paper / dx.doi.org/10.13182/NSE89-A23617
New JEF/EFF Based MATXS-Formatted Nuclear Data Libraries
Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 298-301
Technical Note / dx.doi.org/10.13182/NSE89-A23618
