Volume 105
Number 1 | Number 2 | Number 3 | Number 4
Number 1
A Multiple Balance Approach for Differencing the Sn Equations
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 1-15
Technical Paper / dx.doi.org/10.13182/NSE90-A19208
Discrete Nodal and Sn Transport Methods for Irregularly Shaped Shields
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 16-30
Technical Paper / dx.doi.org/10.13182/NSE90-A19209
Stability Analysis of Coarse-Mesh Rebalance
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 31-39
Technical Paper / dx.doi.org/10.13182/NSE88-117
Vectorization of Diffusion Computations in the Presence of Periodic Boundary Conditions
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 40-51
Technical Paper / dx.doi.org/10.13182/NSE90-A19211
Three-Dimensional Multiregion Sn Solutions of the Spencer-Lewis Electron Transport Equation
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 52-58
Technical Paper / dx.doi.org/10.13182/NSE90-A19212
The Exact Kernel (I*) Method Applied to the Charged-Particle Transport Equation
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 59-78
Technical Paper / dx.doi.org/10.13182/NSE90-A19213
Alpha-Particle Transport and Thermonuclear Burn in Mixtures
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 79-87
Technical Paper / dx.doi.org/10.13182/NSE90-A19214
Test Problems in Radiative Transfer Calculations
Nuclear Science and Engineering / Volume 105 / Number 1 / May 1990 / Pages 88-104
Technical Paper / dx.doi.org/10.13182/NSE90-A19215
Number 2
Calculation of Fuel Penetration and Freezing in Channels with a Two-Phase Flow Code
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 105-122
Technical Paper / dx.doi.org/10.13182/NSE90-A23741
Chaotic Dynamics of a Triply-Forced Two-Phase Flow System
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 123-135
Technical Paper / dx.doi.org/10.13182/NSE90-A23742
Application of Krylov Subspace Methods in Fluid Dynamics
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 136-141
Technical Paper / dx.doi.org/10.13182/NSE90-A23743
A Rigorous Mathematical Technique for Reactor Dynamics: Application to Safe Plutonium Recycling
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 142-159
Technical Paper / dx.doi.org/10.13182/NSE90-A23744
Development of a Technique for the Practical Implementation of Higher Order Perturbation Methods
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 160-173
Technical Paper / dx.doi.org/10.13182/NSE90-A23745
A State Space Search Technique for Optimizing the Shape of a Cold Neutron Source
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 174-183
Technical Paper / dx.doi.org/10.13182/NSE90-A23746
The Multigroup and Cylindrical Geometry Formulation of the Fully Coupled Sn/Monte Carlo Method
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 184-190
Technical Paper / dx.doi.org/10.13182/NSE90-A23747
A Diffusion-Accelerated Sn Transport Method for Radiation Transport on a General Quadrilateral Mesh
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 191-197
Technical Paper / dx.doi.org/10.13182/NSE90-A23748
A First-Collision Source Method That Satisfies Discrete Sn Transport Balance
Nuclear Science and Engineering / Volume 105 / Number 2 / June 1990 / Pages 198-203
Technical Paper / dx.doi.org/10.13182/NSE90-A23749
Number 3
The Density and Compressibility of Liquid (U,Pu)-Mixed Oxide
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 205-217
Technical Paper / dx.doi.org/10.13182/NSE90-A19186
Neutron Kinetics Investigations at the LR-0 Zero-Power Reactor
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 218-232
Technical Paper / dx.doi.org/10.13182/NSE90-A19187
Gamma-Ray Activation and Passive Neutron Methods for Nondestructive Assay of Spent-Fuel Assemblies
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 233-243
Technical Paper / dx.doi.org/10.13182/NSE90-A19188
Analysis of Sample and Fuel Pin Irradiation Experiments in Phénix for Basic Nuclear Data Validation
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 244-255
Technical Paper / dx.doi.org/10.13182/NSE90-A19189
Variational Formulation of a Higher Order Nodal Diffusion Method
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 256-270
Technical Paper / dx.doi.org/10.13182/NSE90-A19190
Wiener-Hopf Technique Solution to a Rewetting Model with Precursory Cooling
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 271-277
Technical Paper / dx.doi.org/10.13182/NSE90-A19191
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 278-289
Technical Paper / dx.doi.org/10.13182/NSE90-A19192
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 290-296
Technical Notes / dx.doi.org/10.13182/NSE90-A19193
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 297-299
Technical Notes / dx.doi.org/10.13182/NSE90-A19194
Number 4
Measurements of the Total Pressure from Irradiated (U,Pu)-Mixed Oxide
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 303-318
Technical Paper / dx.doi.org/10.13182/NSE90-A21467
Neutron and Gamma-Ray Spectra from a Variety of Materials Bombarded with 14-MeV Neutrons
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 319-340
Technical Paper / dx.doi.org/10.13182/NSE90-A21468
Determination of the Optical Constants of Liquid UO2 in the Near Infrared at 1064 nm
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 341-348
Technical Paper / dx.doi.org/10.13182/NSE90-A21469
Multipoint Schemes for the Solution of the Diffusion Equation by Vectorial Computation
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 349-370
Technical Paper / dx.doi.org/10.13182/NSE90-A21470
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 371-382
Technical Paper / dx.doi.org/10.13182/NSE90-A21471
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 383-390
Technical Paper / dx.doi.org/10.13182/NSE90-A21472
Convective Heat Transfer in a Sealed Vertical Storage Cask Containing Spent-Fuel Canisters
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 391-403
Technical Paper / dx.doi.org/10.13182/NSE90-A21473
Diagonally Dominant Enhancement Methods for Matrix Solvers in RELAP5
Nuclear Science and Engineering / Volume 105 / Number 4 / August 1990 / Pages 404-408
Technical Paper / dx.doi.org/10.13182/NSE90-A21474
