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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE91-A23848
Number 2
Measurement of the 10B(n, αo)/10B(n,αγ) Ratio Versus Neutron Energy
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 113-119
Technical Paper | doi.org/10.13182/NSE91-A28510
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 120-127
Technical Paper | doi.org/10.13182/NSE91-A28511
Calculation of Activation Cross Sections for Molybdenum Isotopes
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 128-141
Technical Paper | doi.org/10.13182/NSE91-A28512
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 142-149
Technical Paper | doi.org/10.13182/NSE91-A28513
Monte Carlo Next-Event Estimates from Thermal Collisions
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 150-157
Technical Paper | doi.org/10.13182/NSE91-A28514
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 158-170
Technical Paper | doi.org/10.13182/NSE91-A28515
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 171-187
Technical Paper | doi.org/10.13182/NSE91-A28516
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 188-199
Technical Paper | doi.org/10.13182/NSE91-A28517
Improved Pressurized Water Reactor Radial Reflector Modeling in Nodal Analysis
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 200-214
Technical Note | doi.org/10.13182/NSE91-A28518
Absolute Measurements of the 197Au(n, γ)198Au Cross Section for Fast Neutrons
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 215-220
Technical Note | doi.org/10.13182/NSE91-A28519
Number 3
Evaluation of Liquid-Metal Reactor Design Options for Reduction of Sodium Void Worth
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 221-266
Technical Paper | doi.org/10.13182/NSE91-A23851
A Neutron Source Imaging Detector for Nuclear Arms Treaty Verification
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 267-277
Technical Paper | doi.org/10.13182/NSE91-A23852
Uncertainty in the Burnup Reactivity Swing of Liquid-Metal Fast Reactors
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 278-296
Technical Paper | doi.org/10.13182/NSE91-A23853
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 297-303
Technical Paper | doi.org/10.13182/NSE91-A23854
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 304-318
Technical Paper | doi.org/10.13182/NSE91-A23855
Measurement of the 19F(n,2n)18F Cross Section from 18 to 27 MeV
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 319-323
Technical Note | doi.org/10.13182/NSE91-A23856
Number 4
Monitoring Pressurized Water Reactor Transients Using Reactor Coolant Pumps
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 325-340
Technical Paper | doi.org/10.13182/NSE91-A23858
Fission Cross-Section Measurements of 247Cm, 254Es, and 250Cf from 0.1 eV to 80 keV
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 341-349
Technical Paper | doi.org/10.13182/NSE91-A23859
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 350-359
Technical Paper | doi.org/10.13182/NSE91-A23860
A Consistent Technique for the Global Homogenization of a Pressurized Water Reactor Assembly
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 360-372
Technical Paper | doi.org/10.13182/NSE109-360
Mitigation of Singularity Problems in Gamma-Ray Transport in Spherical Systems
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 373-379
Technical Paper | doi.org/10.13182/NSE91-A23862
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 380-390
Technical Paper | doi.org/10.13182/NSE91-A23863
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 391-400
Technical Paper | doi.org/10.13182/NSE91-A23864
Heating-Induced Damping of Density Perturbations in Nuclear-Reactor-Pumped Lasers
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 401-410
Technical Paper | doi.org/10.13182/NSE91-A23865
Antiproton-Boosted Microfission
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 411-415
Technical Paper | doi.org/10.13182/NSE91-A23866
Approximate Estimators for Fluence at a Point in Monte Carlo Center-of-Mass Neutron Transport
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 416-422
Technical Note | doi.org/10.13182/NSE91-A23867