Number 1 | Number 2 | Number 3
On the Evaluation of Discrepant Scientific Data with Unrecognized Errors
Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 1-17
Technical Paper / dx.doi.org/10.13182/NSE09-37A
Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 18-44
Technical Paper / dx.doi.org/10.13182/NSE09-37B
Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 45-100
Technical Paper / dx.doi.org/10.13182/NSE09-37C
Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 101-116
Technical Paper / dx.doi.org/10.13182/NSE08-90
The 235U(n,f) Prompt Fission Neutron Spectrum at 100 K Input Neutron Energy
Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 117-127
Technical Paper / dx.doi.org/10.13182/NSE09-25
Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 128-130
Letter to the Editor / dx.doi.org/10.13182/NSE09-58L
Nuclear Science and Engineering / Volume 165 / Number 1 / May 2010 / Pages 130-131
Letter to the Editor / dx.doi.org/10.13182/NSE09-58R
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 133-148
Technical Paper / dx.doi.org/10.13182/NSE08-48
Asymptotic Diffusion-Limit Accuracy of S
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 149-169
Technical Paper / dx.doi.org/10.13182/NSE08-66
Adaptive Three-Dimensional Monte Carlo Functional-Expansion Tallies
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 170-179
Technical Paper / dx.doi.org/10.13182/NSE08-68
Transient Two-Dimensional Hydrodynamic Experiments
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 180-199
Technical Paper / dx.doi.org/10.13182/NSE08-18
Re-Analysis of Recent Neutron Diffusion and Transmission Measurements in Nuclear Graphite
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 200-209
Technical Paper / dx.doi.org/10.13182/NSE09-48
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 210-223
Technical Paper / dx.doi.org/10.13182/NSE09-27
Cross Sections for 239Pu(n,f) and 241Pu(n,f) in the Range E
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 224-231
Technical Paper / dx.doi.org/10.13182/NSE09-41
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 232-239
Technical Note / dx.doi.org/10.13182/NSE09-23TN
Nuclear Science and Engineering / Volume 165 / Number 2 / June 2010 / Pages 240-244
Technical Note / dx.doi.org/10.13182/NSE09-35TN
Automated Design and Optimization of Pebble-Bed Reactor Cores
Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 245-269
Technical Paper / dx.doi.org/10.13182/NSE08-89
Spatial Corrections for Pulsed-Neutron Reactivity Measurements
Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 270-282
Technical Paper / dx.doi.org/10.13182/NSE09-32
Exact Regional Monte Carlo Weight Cancellation for Second Eigenfunction Calculations
Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 283-291
Technical Paper / dx.doi.org/10.13182/NSE09-62
A Transport Acceleration Scheme for Multigroup Discrete Ordinates with Upscattering
Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 292-304
Technical Paper / dx.doi.org/10.13182/NSE09-28
Goal-Oriented h-Adaptivity for the Multigroup SP
Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 305-319
Technical Paper / dx.doi.org/10.13182/NSE09-34
Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 320-330
Technical Paper / dx.doi.org/10.13182/NSE09-47
The Newton-Krylov Method Applied to Negative-Flux Fixup in SN Transport Calculations
Nuclear Science and Engineering / Volume 165 / Number 3 / July 2010 / Pages 331-341
Technical Paper / dx.doi.org/10.13182/NSE09-51