Number 1 | Number 2 | Number 3
Nuclear Science and Engineering / Volume 187 / Number 1 / July 2017 / Pages 1-26
Technical Paper / dx.doi.org/10.1080/00295639.2017.1294931
Nuclear Science and Engineering / Volume 187 / Number 1 / July 2017 / Pages 27-48
Technical Paper / dx.doi.org/10.1080/00295639.2016.1275848
A Depletion System Compression Method Based on Quantitative Significance Analysis
Nuclear Science and Engineering / Volume 187 / Number 1 / July 2017 / Pages 49-69
Technical Paper / dx.doi.org/10.1080/00295639.2017.1297079
Thick and Thin Target 7Li(p,n)7Be Neutron Spectra Below the Three-Body Breakup Reaction Threshold
Nuclear Science and Engineering / Volume 187 / Number 1 / July 2017 / Pages 70-80
Technical Paper / dx.doi.org/10.1080/00295639.2017.1291053
Nuclear Science and Engineering / Volume 187 / Number 1 / July 2017 / Pages 81-99
Technical Paper / dx.doi.org/10.1080/00295639.2017.1292090
Nuclear Science and Engineering / Volume 187 / Number 1 / July 2017 / Pages 100-106
Technical Paper / dx.doi.org/10.1080/00295639.2017.1292089
Calculations and Analysis of n+93Nb Reaction
Nuclear Science and Engineering / Volume 187 / Number 2 / August 2017 / Pages 107-126
Technical Paper / dx.doi.org/10.1080/00295639.2017.1295699
Impact of 235U Resonance Parameter Evaluation in the Reactivity Prediction
Nuclear Science and Engineering / Volume 187 / Number 2 / August 2017 / Pages 127-141
Technical Paper / dx.doi.org/10.1080/00295639.2017.1301739
Batch and History Sampling for Fixed-Source Monte Carlo Problems
Nuclear Science and Engineering / Volume 187 / Number 2 / August 2017 / Pages 142-153
Technical Paper / dx.doi.org/10.1080/00295639.2017.1312944
Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energy Covariance Data
Nuclear Science and Engineering / Volume 187 / Number 2 / August 2017 / Pages 154-165
Technical Paper / dx.doi.org/10.1080/00295639.2017.1307031
Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly
Nuclear Science and Engineering / Volume 187 / Number 2 / August 2017 / Pages 166-184
Technical Paper / dx.doi.org/10.1080/00295639.2017.1312931
Nuclear Science and Engineering / Volume 187 / Number 2 / August 2017 / Pages 185-201
Technical Paper / dx.doi.org/10.1080/00295639.2017.1307048
Reactor Neutronics: Impact of Fissile Material
Nuclear Science and Engineering / Volume 187 / Number 2 / August 2017 / Pages 202-211
Technical Paper / dx.doi.org/10.1080/00295639.2017.1312933
Nuclear Science and Engineering / Volume 187 / Number 3 / September 2017 / Pages 213-239
Technical Paper / dx.doi.org/10.1080/00295639.2017.1312941
Nuclear Science and Engineering / Volume 187 / Number 3 / September 2017 / Pages 240-253
Technical Paper / dx.doi.org/10.1080/00295639.2017.1320891
Nuclear Science and Engineering / Volume 187 / Number 3 / September 2017 / Pages 254-267
Technical Paper / dx.doi.org/10.1080/00295639.2017.1320892
MC2-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis
Nuclear Science and Engineering / Volume 187 / Number 3 / September 2017 / Pages 268-290
Technical Paper / dx.doi.org/10.1080/00295639.2017.1320893
Nuclear Science and Engineering / Volume 187 / Number 3 / September 2017 / Pages 291-301
Technical Paper / dx.doi.org/10.1080/00295639.2017.1312937
Nuclear Science and Engineering / Volume 187 / Number 3 / September 2017 / Pages 302-311
Technical Paper / dx.doi.org/10.1080/00295639.2017.1323505