A Study of the Release of Radioactive Metallic Isotopes from High-Temperature Gas-Cooled Reactors
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 201-213
Technical Paper / dx.doi.org/10.13182/NSE68-A21086
Removal of Water and Carbon Dioxide from Helium Coolants by Molecular Sieves
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 214-223
Technical Paper / dx.doi.org/10.13182/NSE68-A21087
Inelastic Scattering of Thermal Neutrons in Graphite
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 224-236
Technical Paper / dx.doi.org/10.13182/NSE68-A21088
Criticality Measurements on Nearly Homogeneous Enriched Uranium-Graphite Systems
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 237-250
Technical Paper / dx.doi.org/10.13182/NSE68-A21089
Analysis of Brookhaven 235U-Graphite Critical Experiments
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 251-262
Technical Paper / dx.doi.org/10.13182/NSE68-A21090
Analysis of a Set of Critical Homogeneous U-H2O Spheres
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 263-274
Technical Paper / dx.doi.org/10.13182/NSE68-A21091
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 275-284
Technical Paper / dx.doi.org/10.13182/NSE68-A21092
Streaming Effects and Collision Probabilities in Lattices
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 285-307
Technical Paper / dx.doi.org/10.13182/NSE68-3
The Calculation of Neutron Flux Ratios in Critical Systems by the Indirect Variational Method
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 308-312
Technical Paper / dx.doi.org/10.13182/NSE68-A21094
An Analysis of Methods for Calculating Spatially Dependent Neutron Slowing Down Distributions
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 313-327
Technical Paper / dx.doi.org/10.13182/NSE68-A21095
Linear Energy Transformation for Gamma-Ray Monte Carlo Calculations
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 328-329
Technical Note / dx.doi.org/10.13182/NSE68-A21096
Evaluation of Neutron Absorption Rates by Activation Measurements of Spectral Indexes
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 329-331
Technical Note / dx.doi.org/10.13182/NSE68-A21097
Self-Shielding Factors for Scattering Dominant Neutron Resonances
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 331-332
Technical Note / dx.doi.org/10.13182/NSE68-A21098
Sensitivity of Neutron Transport in Oxygen to Various Cross-Section Sets
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 332-336
Technical Note / dx.doi.org/10.13182/NSE68-A21099
Applications of a Macroscopic Formulation of Transport Theory
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 336-339
Technical Note / dx.doi.org/10.13182/NSE68-A21100
Overlapping Group Methods with Discontinuous Trial Functions
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 339-341
Technical Note / dx.doi.org/10.13182/NSE68-A21101
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 342-343
Technical Note / dx.doi.org/10.13182/NSE68-A21102
Asymmetric Discontinuities in Synthesis Techniques for Initial-Value Problems
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 343-344
Technical Note / dx.doi.org/10.13182/NSE68-A21103
Verification of a Xenon Spatial Stability Criterion
Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 344-346
Technical Note / dx.doi.org/10.13182/NSE68-A21104