Home / Publications / Journals / Nuclear Science and Engineering / Volume 13

Volume 13

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Number 1

Table of Contents
Reactor Size Sufficient for Stability Against Spatial Xenon Oscillations(Gerald S. Lellouche)
Application of the Pile Oscillator to Large-Neutron-Dose Measurement(Toyojiro Fuketa)
TWENTY GRAND
EQUIPOISE 3
2DGH

The Reactivity Effect of a Regular Array of Empty Cylindrical Channels in a Critical System

J. T. Marti, J. P. Schneeberger

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 1-5

Technical Paper / dx.doi.org/10.13182/NSE62-A26120

The Infinite Neutron Multiplication Constant of Homogeneous Hydrogen-Moderated 2.0 wt%-U₂₃₅-Enriched Uranium

John T. Mihalczo, Victor I. Neeley

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 6-11

Technical Paper / dx.doi.org/10.13182/NSE62-A26121

Reflected-Reactor Kinetics

Charles Erwin Cohn

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 12-17

Technical Paper / dx.doi.org/10.13182/NSE62-A26122

The Neutron Elastic Scattering Cross Section of U²³³ below 20 ev

M. S. Moore, F. B. Simpson

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 18-21

Technical Paper / dx.doi.org/10.13182/NSE62-A26123

Some New Methods of Flux Synthesis

S. Kaplan

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 22-31

Technical Paper / dx.doi.org/10.13182/NSE62-A26124

The Direct Calculation of Diffusion Lengths and Diffusion Hardened Spectra

Gerald P. Calame

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 32-39

Technical Paper / dx.doi.org/10.13182/NSE62-A26125

Inelastic Scattering of Cold Neutrons by Polycrystals

P. G. Khubchandani, R. R. Sharma

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 40-45

Technical Paper / dx.doi.org/10.13182/NSE62-A26126

Boundary, Gap, and Blackness Conditions in the Cylindrical Geometry Spherical Harmonics Approximation

W. W. CLENDENIN

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 46-53

Technical Paper / dx.doi.org/10.13182/NSE62-A26127

Void Volume Ratios During Steady State Local Boiling in Case of Constant Power Distribution

C. Hubers

Nuclear Science and Engineering / Volume 13 / Number 1 / May 1962 / Pages 54-59

Technical Paper / dx.doi.org/10.13182/NSE62-A26128

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

Number 3

Table of Contents
Temperature Histories of Internally Heated Thin Bodies Cooled by Convection and/or Thermal Radiation(Walter Unterberg)
An Improved Technique for the Determination of Short-Lived Fission-Product Gases(Charles W. Townley, Neil E. Miller, Thomas S. Elleman, Duane N. Sunderman)
Silver-Indium-Cadmium, a Control Rod Material for Pressurized Water Reactors(H. W. Graves, Jr., J. J. Lombardo, J. S. Theilacker)
Carbon-14 Compounds(Vernon F. Raaen)

The Correlation of Integral Experiments and High Energy Cross Sections

J. Chernick, H. C. Honeck, P. Michael, S. O. Moore, G. Srikantiah

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 205-214

Technical Paper / dx.doi.org/10.13182/NSE62-A26155

The Thermalization and Diffusion of Neutrons in Heavy Gaseous Moderators

Satoru Katsuragi

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 215-229

Technical Paper / dx.doi.org/10.13182/NSE62-A26156

Thermalization and Diffusion Parameters of Neutrons in Zirconium Hydride

J. W. Meadows, J. F. Whalen

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 230-236

Technical Paper / dx.doi.org/10.13182/NSE62-A26157

The Behavior of Extrapolation Distances in Die-Away Experiments

E. M. Gelbard, J. A. Davis

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 237-244

Technical Paper / dx.doi.org/10.13182/NSE62-A26158

Calorimetric Measurement of Nuclear Heating in a Reactor

C. D. Bopp, R. L. Towns

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 245-249

Technical Paper / dx.doi.org/10.13182/NSE62-A26159

Scattering of Thermal Neutrons in the Doppler Approximation

S. N. Purohit, A. K. Rajagopal

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 250-260

Technical Paper / dx.doi.org/10.13182/NSE62-A26160

Influence of the Moderator Size on the Slowing Down of (D, D) Neutrons in Paraffin Wax

B. Grimeland, S. Messelt, L. Sund

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 261-263

Technical Paper / dx.doi.org/10.13182/NSE62-A26161

Measurements of Neutron Spectra with a Fast Chopper

Erik Johansson, Erik Jonsson

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 264-270

Technical Paper / dx.doi.org/10.13182/NSE62-A26162

Frequency Response of Current Ion Chamber

R. Subramaniam, R. Vedam

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 271-274

Technical Paper / dx.doi.org/10.13182/NSE62-A26163

Thermal Properties of Air-Cooled Graphite Channels

Donald G. Schweitzer

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 275-282

Technical Paper / dx.doi.org/10.13182/NSE62-A26164

Heat Transfer in Sodium-Potassium Alloy

R. A. Baker, Alexander, Sesonske

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 283-288

Technical Paper / dx.doi.org/10.13182/NSE62-A26165

Thermal Neutron Capture Cross Section and Resonance Capture Integral of Ce¹⁴⁴

P. M. Lantz

Nuclear Science and Engineering / Volume 13 / Number 3 / July 1962 / Pages 289-294

Technical Paper / dx.doi.org/10.13182/NSE62-A26166

Number 4

Table of Contents
Theory of Elastic Thin Shells(David Burgreen)
Introduction to Nuclear Science(P. F. Pasqua)
Rare Earth Alloys, A Critical Review of the Alloy Systems of the Rare Earth, Scandium and Yttrium Metals(W. Kermit Anderson)
Protective Construction in a Nuclear Age. Proceedings of the Second Protective Construction Symposium: The Rand Corporation(L. J. Vortman)
Treatment and Disposal of Radioactive Wastes(Abraham S. Goldin)
Criticality Control in Chemical and Metallurgical Plant(Hugh F. Henry)
AIMFIRE(R. A. Blaine)
KERNMAT(S. A. Raje)

Reflector Moderated Reactors

C. B. Mills

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 301-305

Technical Paper / dx.doi.org/10.13182/NSE62-A26172

Thermal Neutron Spectra in Graphite

D. E. Parks, J. R. Beyster, N. F. Wikner

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 306-324

Technical Paper / dx.doi.org/10.13182/NSE62-A26173

Transient Thermal Behavior of Experimental UO₂ Fuel Elements in the Sodium Reactor Experiment (SRE)

J. T. Ream, R. P. Varnes

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 325-337

Technical Paper / dx.doi.org/10.13182/NSE62-A26174

The Effect of Modal Interaction in the Xenon Instability Problem

Geza L. Gyorey

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 338-344

Technical Paper / dx.doi.org/10.13182/NSE62-A26175

Comparison of Flux Ratio Calculations in Lattices by Integral Transport Theory

Yuzo Fukai

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 345-354

Technical Paper / dx.doi.org/10.13182/NSE62-A26176

Fast Reactor Rocket Engines—Criticality

Ralph Cooper

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 355-365

Technical Paper / dx.doi.org/10.13182/NSE62-A26177

A Review of the Methods Used for the Determination of Hydrogen in Uranium

Harold F. Waldron

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 366-373

Technical Paper / dx.doi.org/10.13182/NSE62-A26178

An Improved Procedure for U²³⁵ Isotopic Ratio Analysis in Impure Materials

W. D. Kelley, B. L. Twitty

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 374-377

Technical Paper / dx.doi.org/10.13182/NSE62-A26179

Capsule Irradiations of a Paste of Uranium—10 wt % Molybdenum Powder in NaK

E. C. Kovacic, Paul R. Huebotter, John E. Gates

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 378-384

Technical Paper / dx.doi.org/10.13182/NSE62-A26180

Resonance and Thermal Neutron Self-Shielding in Cobalt Foils and Wires

T. A. Eastwood, R. D. Werner

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 385-390

Technical Paper / dx.doi.org/10.13182/NSE62-A26181

Laboratory-Scale Demonstration of the Fused Salt Volatility Process

G. I. Gathers, R. L. Jolley, E. G Moncrief

Nuclear Science and Engineering / Volume 13 / Number 4 / August 1962 / Pages 391-397

Technical Paper / dx.doi.org/10.13182/NSE62-A26182