Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 1-22
Technical Paper / dx.doi.org/10.13182/NSE00-A2120
Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 23-32
Technical Paper / dx.doi.org/10.13182/NSE00-A2121
Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 33-47
Technical Paper / dx.doi.org/10.13182/NSE99-33
Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 48-56
Technical Paper / dx.doi.org/10.13182/NSE00-A2123
Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 57-63
Technical Paper / dx.doi.org/10.13182/NSE00-A2124
Verification of the Neutron Flux of a Modified Zero-Power Reactor Using a Neutron Activation Method
Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 64-72
Technical Paper / dx.doi.org/10.13182/NSE00-A2125
A Multigroup Albedo Method for Transport Calculations: Application to the Orphée Core
Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 73-83
Technical Paper / dx.doi.org/10.13182/NSE00-A2126
Nuclide Importance and the Steady-State Burnup Equation
Nuclear Science and Engineering / Volume 135 / Number 1 / May 2000 / Pages 84-102
Technical Paper / dx.doi.org/10.13182/NSE00-A2127