Surface Depletion in the Vacuum Distillation of Metals from Bismuth
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 159-164
Technical Paper / dx.doi.org/10.13182/NSE69-A21131
Simplified Analysis of Coolant Flow and Outlet Temperature in Gas-Cooled Nuclear Reactor Cores
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 165-175
Technical Paper / dx.doi.org/10.13182/NSE69-A21132
Linear Dynamics Model for Steam Cooled Fast Power Reactors
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 176-189
Technical Paper / dx.doi.org/10.13182/NSE69-A21133
Two-Phase Fluid Modeling—The Critical Heat Flux
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 190-199
Technical Paper / dx.doi.org/10.13182/NSE69-A21134
An Integrated Analytical Model for the Evaluation of Two-Phase Flow Stability
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 200-210
Technical Paper / dx.doi.org/10.13182/NSE69-A21135
Instability Bounds in Linearly Stable Systems
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 211-219
Technical Paper / dx.doi.org/10.13182/NSE69-A21136
Shielding of Neutrons from 80-MeV Alpha-Particle Bombardment of Tantalum
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 220-226
Technical Paper / dx.doi.org/10.13182/NSE69-A21137
Time Spectra from Spheres Pulsed with 14-MeV Neutrons
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 227-239
Technical Paper / dx.doi.org/10.13182/NSE69-A21138
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 240-248
Technical Paper / dx.doi.org/10.13182/NSE69-A21139
Reactor-Noise Analysis: The Covariance Method via Polarity Detection
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 249-258
Technical Paper / dx.doi.org/10.13182/NSE69-A21140
Measurement of the Thermal-Neutron Extrapolation Length in a Pulsed Water System
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 259-266
Technical Paper / dx.doi.org/10.13182/NSE69-A21141
Critical Measurements on an Enriched Uranium Solution System
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 267-276
Technical Paper / dx.doi.org/10.13182/NSE69-A21142
The Effect of Linearly Anisotropic Neutron Scattering on Disadvantage Factor Calculations
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 277-282
Technical Paper / dx.doi.org/10.13182/NSE69-A21143
Modeling Relationships for Radiation Transport Within Ducts and Other Cavities in Shields
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 283-285
Technical Note / dx.doi.org/10.13182/NSE69-A21144
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 285-289
Technical Note / dx.doi.org/10.13182/NSE69-A21145
A Method for Treating the Neutron Leakage in Small Exponential Cores
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 289-295
Technical Note / dx.doi.org/10.13182/NSE69-A21146
Monte Carlo Interpretation of a 238U Spherical Shell Transmission Experiment at 23 keV
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 295-297
Technical Note / dx.doi.org/10.13182/NSE69-A21147
Multilevel Effects on Infinite Dilution Resonance Integrals
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 297-298
Technical Note / dx.doi.org/10.13182/NSE69-A21148