Volume 109
Number 1
An R Matrix Analysis of the 235U Neutron-Induced Cross Sections up to 500 eV
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 1-17
Technical Paper / dx.doi.org/10.13182/NSE91-A23840
Pairing Corrections and Spin Cutoff Factors in Exciton Level Densities for Two Kinds of Fermions
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 18-25
Technical Paper / dx.doi.org/10.13182/NSE91-A23841
Modeling of Fission Product Release and Transport for Severe Fuel Damage Analyses
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 26-38
Technical Paper / dx.doi.org/10.13182/NSE91-A23842
High-Temperature Hydrogen Combustion in Reactor Safety Applications
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 39-48
Technical Paper / dx.doi.org/10.13182/NSE91-A23843
The PN Theory as an Asymptotic Limit of Transport Theory in Planar Geometry —I: Analysis
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 49-75
Technical Paper / dx.doi.org/10.13182/NSE91-A23844
The PN Theory as an Asymptotic Limit of Transport Theory in Planar Geometry —II: Numerical Results
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 76-85
Technical Note / dx.doi.org/10.13182/NSE91-A23845
Effects of Changing the Random Number Stride in Monte Carlo Calculations
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 86-91
Technical Note / dx.doi.org/10.13182/NSE91-A23846
Analysis of Beta-Ray Data Important to Decay Heat Predictions
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 92-102
Technical Note / dx.doi.org/10.13182/NSE91-A23847
Application of Knowledge-Based Methods to In-Core Fuel Management
Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 103-110
Technical Note / dx.doi.org/10.13182/NSE91-A23848
