Number 1 | Number 2 | Number 3
Some Improvements in State/Parameter Estimation Using the Cell-to-Cell Mapping Technique
Nuclear Science and Engineering / Volume 147 / Number 1 / May 2004 / Pages 1-25
Technical Paper / dx.doi.org/10.13182/NSE04-A2415
Krylov Subspace Iterations for Deterministic k-Eigenvalue Calculations
Nuclear Science and Engineering / Volume 147 / Number 1 / May 2004 / Pages 26-42
Technical Paper / dx.doi.org/10.13182/NSE04-1
Nuclear Science and Engineering / Volume 147 / Number 1 / May 2004 / Pages 43-55
Technical Paper / dx.doi.org/10.13182/NSE04-A2417
A Model for Dead-Time Effects in Coincidence Counting
Nuclear Science and Engineering / Volume 147 / Number 1 / May 2004 / Pages 56-62
Technical Paper / dx.doi.org/10.13182/NSE04-A2418
Nuclear Science and Engineering / Volume 147 / Number 1 / May 2004 / Pages 63-72
Technical Paper / dx.doi.org/10.13182/NSE04-A2419
Nuclear Science and Engineering / Volume 147 / Number 1 / May 2004 / Pages 73-82
Technical Paper / dx.doi.org/10.13182/NSE04-A2420
Nuclear Science and Engineering / Volume 147 / Number 1 / May 2004 / Pages 83-91
Technical Note / dx.doi.org/10.13182/NSE04-A2421
Super-Nodal Methods for Space-Time Kinetics
Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 93-126
Technical Paper / dx.doi.org/10.13182/NSE04-A2422
Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 127-147
Technical Paper / dx.doi.org/10.13182/NSE03-64
Optimized Algorithm for Collision Probability Calculations in Cubic Geometry
Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 148-157
Technical Paper / dx.doi.org/10.13182/NSE04-A2424
Singular Solutions, Integral Transport Theory, and the Sn Method
Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 158-166
Technical Paper / dx.doi.org/10.13182/NSE04-A2425
Neutron Flux Distribution in a Cavity with a Point Source
Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 167-175
Technical Paper / dx.doi.org/10.13182/NSE04-A2426
Acceleration of Response Matrix Method Using Cross-Section Scaling
Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 176-184
Technical Paper / dx.doi.org/10.13182/NSE04-A2427
Evaluation of the Efficiency of Gamma Spectrometers for Measuring Volumetric Samples
Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 185-188
Technical Paper / dx.doi.org/10.13182/NSE04-A2428
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 189-203
Technical Paper / dx.doi.org/10.13182/NSE03-105CR
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 204-217
Technical Paper / dx.doi.org/10.13182/04-54CR
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 218-248
Technical Paper / dx.doi.org/10.13182/NSE02-14
Discrete Ordinates Solutions for Highly Forward Peaked Scattering
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 249-274
Technical Paper / dx.doi.org/10.13182/NSE04-A2432
Unified Nodal Method for Solution to the Space-Time Kinetics Problems
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 275-291
Technical Paper / dx.doi.org/10.13182/NSE04-A2433
A Stochastic Problem Arising in the Storage of Radioactive Waste
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 292-306
Technical Paper / dx.doi.org/10.13182/NSE04-A2434
Critical Experiments with Highly Enriched Uranium and Matrix Elements (Si, Mg, Al, Gd, and Fe)
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 307-318
Technical Paper / dx.doi.org/10.13182/NSE04-A2435
Nuclear Science and Engineering / Volume 147 / Number 3 / July 2004 / Pages 319-322
Technical Note / dx.doi.org/10.13182/NSE04-A2436