Study of Lithium Mobility in Irradiated Silicon
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 175-182
Technical Paper / dx.doi.org/10.13182/NSE68-A18229
Geometry and Barrier Attenuation of Cobalt-60 Gamma Rays by a Vertical Steel Slab
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 183-190
Technical Paper / dx.doi.org/10.13182/NSE68-A18230
A Study of Fission-Neutron Spectra with High-Energy Activation Detectors. Part II: Fission Spectra
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 191-206
Technical Paper / dx.doi.org/10.13182/NSE68-A18231
The Energy Spectrum of Fast Neutrons Slowing Down from a Fission Source in a Homogeneous Medium
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 207-214
Technical Paper / dx.doi.org/10.13182/NSE68-A18232
Cross-Spectral Density Measurements in a Coupled-Core Reactor
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 215-221
Technical Paper / dx.doi.org/10.13182/NSE68-A18233
Analysis of Pulsed Fast-Neutron Spectra in Multiplying Assemblies
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 222-233
Technical Paper / dx.doi.org/10.13182/NSE68-A18234
The Statistical Estimation of Thermal-Neutron Cross Sections
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 234-240
Technical Paper / dx.doi.org/10.13182/NSE68-A18235
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 241-246
Technical Paper / dx.doi.org/10.13182/NSE68-A18236
Low-Flux Measurement of 235U Epicadmium Capture-to-Fission Ratio
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 247-253
Technical Paper / dx.doi.org/10.13182/NSE68-A18237
Neutron Scattering from Light Water
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 254-271
Technical Paper / dx.doi.org/10.13182/NSE68-A18238
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 272-281
Technical Paper / dx.doi.org/10.13182/NSE68-A18239
Monte Carlo Analysis of Nuclear Reactor Fluctuation Models
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 282-294
Technical Paper / dx.doi.org/10.13182/NSE68-A18240
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 295-303
Technical Paper / dx.doi.org/10.13182/NSE31-295
Numerical Solution of the Time-Dependent Multigroup Diffusion Equations
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 304-313
Technical Paper / dx.doi.org/10.13182/NSE68-A18242
Comparison of Neutron-Transport and Diffusion Theories of Isotropic Scattering
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 314-317
Technical Paper / dx.doi.org/10.13182/NSE68-A18243
Accuracy of Transport Theory Calculations of an Anisotropic Neutron Flux
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 318-324
Technical Paper / dx.doi.org/10.13182/NSE68-A18244
A Strategy for the Application of Space-Angle Synthesis to Practical Problems in Neutron Transport
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 325-336
Technical Paper / dx.doi.org/10.13182/NSE68-A18245
Effect of Property Variation on the Turbulent Flow of Gases in Tubes: The Thermal Entry
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 337-341
Technical Note / dx.doi.org/10.13182/NSE68-A18246
Total Cross Sections of Na, K, and Ca for 14-MeV Neutrons
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 341-343
Technical Note / dx.doi.org/10.13182/NSE68-A18247
Absolute Neutron Yields from Thick Target NATC(α,n)
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Page 343
Technical Note / dx.doi.org/10.13182/NSE68-A18248
Comparison of Beryllium Photoneutron Decay Sets Using Experimental SNAP Data
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 343-346
Technical Note / dx.doi.org/10.13182/NSE68-A18249
Suggested Procedures for Utilizing MUFT Resonance Parameters to Include Doppler Broadening
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 346-349
Technical Note / dx.doi.org/10.13182/NSE68-A18250
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 349-353
Technical Note / dx.doi.org/10.13182/NSE68-A18251
Anomalies Arising from the Use of Adjoint Weighting in a Collapsed Group-Space Synthesis Model
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 354-358
Technical Note / dx.doi.org/10.13182/NSE68-A18252
Flux Tilting in a Two-Zone Reactor
Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 358-359
Technical Note / dx.doi.org/10.13182/NSE68-A18253