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Volume 35

Number 2

Surface Depletion in the Vacuum Distillation of Metals from Bismuth

R. F. Bradley, D. S. Webster

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

G. Melese-d'Hospital

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

Heinz Vollmer

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

F. W. Staub

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

Niels Kjaer-Pedersen

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

Louis M. Shotkin

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

William W. Wadman III

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

Luisa F. Hansen, John D. Anderson, Eugene Goldberg, Ernest F. Plechaty, Marion L. Stelts, Calvin Wong

Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 227-239

Technical Paper / dx.doi.org/10.13182/NSE69-A21138

An Analysis of the Time-Dependent Neutron Transport Equation with Delayed Neutrons by the Method of Matched Asymptotic Expansions

W. L. Hendry, G. I. Bell

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

Nicola Pacilio

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

S. Shalev, G. Shani, Z. Fishelson, and Y. Ronen

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

Robert E. Rothe

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

G. R. Bond, C. E. Siewert

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

Justo Diaz, A. B. Chilton

Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 283-285

Technical Note / dx.doi.org/10.13182/NSE69-A21144

Analysis of the Dieaway of Prompt Neutrons with Two-Group Time-Dependent Diffusion Equation in Reflected Reactors

R. A. Karam

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

Hans Ludewig

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

L. B. Miller, W. P. Poenitz

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

E. M. Pennington, D. A. Sargis

Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 297-298

Technical Note / dx.doi.org/10.13182/NSE69-A21148