Number 1 | Number 2 | Number 3
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 1-14
Technical Paper / dx.doi.org/10.13182/NSE08-A2734
On-the-Fly Diagnostics of Particle Population in Iterated-Source Monte Carlo Methods
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 15-27
Technical Paper / dx.doi.org/10.13182/NSE08-A2735
Anisotropy and Particle Conservation for Trajectory-Based Deterministic Methods
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 28-39
Technical Paper / dx.doi.org/10.13182/NSE08-A2736
A Coupled Diffusion Synthetic Acceleration for Binary Stochastic Mixture Transport Iterations
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 40-48
Technical Paper / dx.doi.org/10.13182/NSE08-A2737
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 49-67
Technical Paper / dx.doi.org/10.13182/NSE05-100
New Evaluation of the 99Tc Neutron-Induced Cross Sections for the ENDF/B-VII.0 Library
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 68-77
Technical Paper / dx.doi.org/10.13182/NSE08-A2739
Theoretical Calculations of n + 232,234,236,238,240U Reaction Cross Sections
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 78-87
Technical Paper / dx.doi.org/10.13182/NSE08-A2740
Nuclear Science and Engineering / Volume 158 / Number 1 / January 2008 / Pages 88-96
Technical Note / dx.doi.org/10.13182/NSE08-A2741
Adjoint Sensitivity Analysis of Dynamic Reliability Models Based on Markov Chains - I: Theory
Nuclear Science and Engineering / Volume 158 / Number 2 / February 2008 / Pages 97-113
Technical Paper / dx.doi.org/10.13182/NSE08-A2742
Nuclear Science and Engineering / Volume 158 / Number 2 / February 2008 / Pages 114-153
Technical Paper / dx.doi.org/10.13182/NSE08-A2743
Nuclear Science and Engineering / Volume 158 / Number 2 / February 2008 / Pages 154-163
Technical Paper / dx.doi.org/10.13182/NSE06-23
Nuclear Science and Engineering / Volume 158 / Number 2 / February 2008 / Pages 164-193
Technical Paper / dx.doi.org/10.13182/NSE08-A2745
Nuclear Science and Engineering / Volume 158 / Number 2 / February 2008 / Pages 194-202
Technical Paper / dx.doi.org/10.13182/NSE08-A2746
Calculation of the Minimum Critical Mass of Fissile Nuclides
Nuclear Science and Engineering / Volume 158 / Number 2 / February 2008 / Pages 203-209
Technical Note / dx.doi.org/10.13182/NSE08-A2747
Some Observations on Spontaneous Fission Nuclei
Nuclear Science and Engineering / Volume 158 / Number 2 / February 2008 / Pages 210-212
Letter To the Editor / dx.doi.org/10.13182/NSE08-A2748
Light Water Reactor Equilibrium Cycle Search Methodology for Assembly-Level Fuel Cycle Analysis
Nuclear Science and Engineering / Volume 158 / Number 3 / March 2008 / Pages 213-230
Technical Paper / dx.doi.org/10.13182/NSE08-A2749
Nuclear Science and Engineering / Volume 158 / Number 3 / March 2008 / Pages 231-243
Technical Paper / dx.doi.org/10.13182/NSE08-A2750
Self-Adaptive Spherical Wavelets for Angular Discretizations of the Boltzmann Transport Equation
Nuclear Science and Engineering / Volume 158 / Number 3 / March 2008 / Pages 244-263
Technical Paper / dx.doi.org/10.13182/NSE08-A2751
Optimization of Burnable Poison Loading for HTGR Cores with OTTO Refueling
Nuclear Science and Engineering / Volume 158 / Number 3 / March 2008 / Pages 264-271
Technical Paper / dx.doi.org/10.13182/NSE08-A2752
Nuclear Science and Engineering / Volume 158 / Number 3 / March 2008 / Pages 272-283
Technical Paper / dx.doi.org/10.13182/NSE06-120
Influence of Coolant Flow Direction on Criticality Waves
Nuclear Science and Engineering / Volume 158 / Number 3 / March 2008 / Pages 284-288
Technical Paper / dx.doi.org/10.13182/NSE08-A2754
Nuclear Science and Engineering / Volume 158 / Number 3 / March 2008 / Pages 289-298
Technical Note / dx.doi.org/10.13182/NSE06-24TN