Volume 102
Number 1 | Number 2 | Number 3 | Number 4
Number 1
A Multigrid Acceleration Method for the One-Dimensional SN Equations with Anisotropic Scattering
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 1-21
Technical Paper / dx.doi.org/10.13182/NSE89-A23628
Uncertainty and Sensitivity Analysis of a Dry Containment Test Problem for the MAEROS Aerosol Model
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 22-42
Technical Paper / dx.doi.org/10.13182/NSE89-A23629
A Knowledge-Based System for Optimization of Fuel Reload Configurations
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 43-53
Technical Paper / dx.doi.org/10.13182/NSE89-A23630
Solution of Nuclide Burnup Equations Using Transition Probabilities
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 54-63
Technical Paper / dx.doi.org/10.13182/NSE89-A23631
Gamma-Ray Buildup Factors for a Point Isotropic Source in Stratified Spherical Shields
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 64-73
Technical Paper / dx.doi.org/10.13182/NSE88-68
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 74-100
Technical Paper / dx.doi.org/10.13182/NSE89-A23633
A Methodology Quantifying the Range of Applicability of Scaling Laws
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 101-113
Technical Paper / dx.doi.org/10.13182/NSE89-A23634
Conservation of Neutrons in Time-Dependent Slowing Down
Nuclear Science and Engineering / Volume 102 / Number 1 / May 1989 / Pages 114-118
Technical Note / dx.doi.org/10.13182/NSE89-A23635
Number 2
Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 119-133
Technical Paper / dx.doi.org/10.13182/NSE89-A23637
Optimal Control of a Boiling Water Reactor Load-Following Operation
Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 134-139
Technical Paper / dx.doi.org/10.13182/NSE89-A23638
Interface Angular Coupling Reductions in Variational Nodal Methods for Neutron Transport
Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 140-152
Technical Paper / dx.doi.org/10.13182/NSE89-A23639
A Simulation-Based Expert System for Nuclear Power Plant Diagnostics
Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 153-171
Technical Paper / dx.doi.org/10.13182/NSE89-A23640
Time-Dependent Single-Collision Kernels for Integral Transport Theory
Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 172-182
Technical Paper / dx.doi.org/10.13182/NSE89-A23641
Boundary Condition Perturbation Theory for Use in Spatial Homogenization Methods
Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 183-190
Technical Paper / dx.doi.org/10.13182/NSE89-3
Empirical Formulas of Neutron Flux Distributions in Cylindrical Ducts in Water or Concrete Shields
Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 191-209
Technical Paper / dx.doi.org/10.13182/NSE89-A23643
Number 3
Approximate Calculation of the Resonance Integral for Isolated Resonances
Nuclear Science and Engineering / Volume 102 / Number 3 / July 1989 / Pages 211-218
Technical Paper / dx.doi.org/10.13182/NSE89-A27475
A Probabilistic Approach to Quantifying Uncertainties in the Progression of Severe Accidents
Nuclear Science and Engineering / Volume 102 / Number 3 / July 1989 / Pages 219-259
Technical Paper / dx.doi.org/10.13182/NSE89-A27476
A Review of the BETA Experimental Results and Code Comparison Calculations
Nuclear Science and Engineering / Volume 102 / Number 3 / July 1989 / Pages 260-282
Technical Paper / dx.doi.org/10.13182/NSE102-260
Robust Control of a Boiling Water Reactor
Nuclear Science and Engineering / Volume 102 / Number 3 / July 1989 / Pages 283-294
Technical Paper / dx.doi.org/10.13182/NSE89-A27478
Nuclear Science and Engineering / Volume 102 / Number 3 / July 1989 / Pages 295-309
Technical Paper / dx.doi.org/10.13182/NSE89-A27479
Nuclear Science and Engineering / Volume 102 / Number 3 / July 1989 / Pages 310-321
Technical Paper / dx.doi.org/10.13182/NSE89-A27480
Number 4
Expert Opinion in Risk Analysis: The NUREG-1150 Methodology
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 323-331
Technical Paper / dx.doi.org/10.13182/NSE89-A23645
Zero-Variance Solutions for Linear Monte Carlo
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 332-340
Technical Paper / dx.doi.org/10.13182/NSE89-A23646
Physics Experiments and Lifetime Performance of the Light Water Breeder Reactor
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 341-364
Technical Paper / dx.doi.org/10.13182/NSE89-A23647
Depletion Perturbation Theory for the Constrained Equilibrium Cycle
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 365-380
Technical Paper / dx.doi.org/10.13182/NSE89-A23648
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 381-390
Technical Paper / dx.doi.org/10.13182/NSE89-A23649
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 391-407
Technical Paper / dx.doi.org/10.13182/NSE89-A23650
Describing Function Method Applied to Solution of Nonlinear Heat Conduction Equation
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 408-422
Technical Paper / dx.doi.org/10.13182/NSE89-A23651
The Spontaneous Fission Half-Life of 240Pu
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 423-427
Technical Paper / dx.doi.org/10.13182/NSE89-A23652
Cross-Section Measurement of the 3He(n,γ) Reaction at En = 24.5 keV
Nuclear Science and Engineering / Volume 102 / Number 4 / August 1989 / Pages 428-431
Technical Paper / dx.doi.org/10.13182/NSE89-A23653
