Volume 13

Number 2

Table of Contents
Eigenvalues for the Wilkins Equation(E. Garelis)
Effective Diffusion Coefficient in Void Regions(G. Velarde)
The Rare Earths(David H. Gurinsky)
Textbook of Reactor Physics(James H. Marable)
Your Future in Nuclear Energy Fields(Raymond L. Murray)
Mathematical Handbook for Scientists and Engineers(J. Ernest Wilkins, Jr.)

Particle—Liquid Cocurrent Downward Flow Through a Tube with a Restricting Orfice End for Application to a Mobile Fuel Nuclear Reactor System

Wan Yong Chon, Evan C. Kovacic, Frederick G. Hammitt

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 65-74

Technical Paper / dx.doi.org/10.13182/NSE62-A26135

Simulation of the Thermal Processes in the Reactor Core Based on an Exact Solution of the Thermal Diffusion and Heat Flow Equations

W. Ciechanowicz

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 75-79

Technical Paper / dx.doi.org/10.13182/NSE62-A26136

Reactivity Effects Produced by Fluid Motion in a Reactor Core

Bertram Wolfe

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 80-90

Technical Paper / dx.doi.org/10.13182/NSE62-A26137

A Simplified Dynamic Model for the Vibration Frequencies and Critical Coolant Flow Velocities for Reactor Parallel Plate Fuel Assemblies

G. S. Rosenberg, C. K. Youngdahl

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 91-102

Technical Paper / dx.doi.org/10.13182/NSE62-A26138

Gas Chromatography as Applied to Nuclear Technology—I

A. D. Horton

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 103-109

Technical Paper / dx.doi.org/10.13182/NSE62-A26139

An Engineering Physics Method of Calculation Applied to Light-Water Critical Experiments Investigating Nuclear Superheat

R. W. Deutsch

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 110-131

Technical Paper / dx.doi.org/10.13182/NSE62-A26140

Theory of Resonance Absorption of Neutrons

Rubin Goldstein, E. Richard Cohen

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 132-140

Technical Paper / dx.doi.org/10.13182/NSE62-1

The Space-Time Neutron Kinetic Equations Obtained by the Semidirect Variational Method

D. E. Dougherty, C. N. Shen

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 141-148

Technical Paper / dx.doi.org/10.13182/NSE62-A26142

Velocity Dependent Milne's Problem

R. Kladnik, I. Kuščer

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 149-152

Technical Paper / dx.doi.org/10.13182/NSE62-A26143

Development of the Semihomogeneous Fuel Element for a Gas-Cooled Reactor

S. A. Bernsen, H. C. Hopkins, Jr., R. C. Howard

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 153-165

Technical Paper / dx.doi.org/10.13182/NSE62-A26144

Two Methods of Calculating Fast Reactor Control Rod Effect and Their Agreement With Experiment

A. D. Krumbein, J. H. Ray

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 166-170

Technical Paper / dx.doi.org/10.13182/NSE62-A26145

Moments Calculations of the Fermi Age in Moderators and Moderator—Metal Mixtures

G. D. Joanou, A. J. Goodjohn, N. F. Wikner

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 171-189

Technical Paper / dx.doi.org/10.13182/NSE62-A26146

Interaction of Adjacent Neutron Detectors

G. Ronald Dalton

Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 190-196

Technical Paper / dx.doi.org/10.13182/NSE62-A26147