Volume 104
Number 1
A Split-Matrix Method for the Numerical Solution of Two-Phase Flow Equations
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 1-9
Technical Paper / dx.doi.org/10.13182/NSE90-A23696
Fast Three-Dimensional Core Model for Digital Control in Boiling Water Reactors
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 10-25
Technical Paper / dx.doi.org/10.13182/NSE90-A23697
Optimized Two-Dimensional Sn Transport (BISTRO)
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 26-33
Technical Paper / dx.doi.org/10.13182/NSE90-1
Thermal Disadvantage Factor: An Efficient Calculation
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 34-39
Technical Paper / dx.doi.org/10.13182/NSE90-A23699
Energy Dependence of Neutron Self-Shielding Factors in an Isolated Resonance
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 40-45
Technical Paper / dx.doi.org/10.13182/NSE90-A23700
Iron and Cadmium Capture Gamma-Ray Photofission Measurements
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 46-52
Technical Paper / dx.doi.org/10.13182/NSE90-A23701
Measurement of Prompt Neutron Decay Constant and Large Subcriticality by the Feynman-α Method
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 53-65
Technical Paper / dx.doi.org/10.13182/NSE104-53
Feasibility and Incentives for Burnup Credit in Spent-Fuel Transport Casks
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 66-77
Technical Paper / dx.doi.org/10.13182/NSE90-A23703
Global Optimization and Sensitivity Analysis
Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 78-88
Technical Paper / dx.doi.org/10.13182/NSE90-A23704
