Volume 139
Number 1
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 1-23
Technical Paper / dx.doi.org/10.13182/NSE00-31
Threshold Reaction Cross Sections of Nickel Isotopes, Averaged Over a 235U Fission Neutron Spectrum
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 24-32
Technical Paper / dx.doi.org/10.13182/NSE01-A2219
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 33-46
Technical Paper / dx.doi.org/10.13182/NSE00-69
A Transport Condensed History Algorithm for Electron Monte Carlo Simulations
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 47-65
Technical Paper / dx.doi.org/10.13182/NSE01-A2221
Neutron Transport in Spatially Random Media: Eigenvalue Problems
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 66-77
Technical Paper / dx.doi.org/10.13182/NSE01-A2222
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 78-95
Technical Paper / dx.doi.org/10.13182/NSE01-A2223
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 96-104
Technical Paper / dx.doi.org/10.13182/NSE01-A2224
An Alternate Formulation of the Nodal Expansion Method
Nuclear Science and Engineering / Volume 139 / Number 1 / September 2001 / Pages 105-110
Technical Note / dx.doi.org/10.13182/NSE01-A2225
