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Volume 20

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Number 1

Table of Contents
A Theorem Concerning the Slowing-Down Equation(M. W. Dyos)
Swelling of Irradiated Uranium-Zirconium Alloys on Annealing(B. A. Loomis)
A Generalization of the Endpoint Method(K. O. Thielheim)
System Analysis of Nuclear Reactor Dynamics(George G. Biro)
The Technology of the Treatment of Uranium Concentrates(Albert A. Jonke)
Heavy Water Lattices(Charles N. Kelber)

Fatigue Design Basis for Zircaloy Components

W. J. O'Donnell, B. F. Langer

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE64-A19269

Processing of Graphite Reactor Fuels Containing Coated Particles and Ceramics

R. E. Blanco, G. I. Cathers, L. M. Ferris, T. A. Gens, R. W. Horton, E. L. Nicholson

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 13-22

Technical Paper / dx.doi.org/10.13182/NSE64-A19270

A New Liquid Scintillator for Thermal Neutron Detection

H. H. Ross, R. E. Yerick

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 23-27

Technical Paper / dx.doi.org/10.13182/NSE64-A19271

Laminar, Turbulent, and Transition Gas Flow in Porous Media

E. Creutz

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 28-44

Technical Paper / dx.doi.org/10.13182/NSE64-A19272

Thermally Induced Vibrations of Concentric Thin Spherical Shells

Arthur L. Austin

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 45-52

Technical Paper / dx.doi.org/10.13182/NSE64-A19273

Spatial-Distribution Functions for Calculating Neutron Densities by Monte Carlo

Harvey J. Amster, Wilson K. Talley

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 53-59

Technical Paper / dx.doi.org/10.13182/NSE64-A19274

Prompt-Neutron Lifetime in Critical Enriched-Uranium Metal Cylinders and Annuli

John T. Mihalczo

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 60-65

Technical Paper / dx.doi.org/10.13182/NSE20-60

Point-to-Point Kernel Analysis of an Experiment to Determine Wall Penetration of a Squarebased Concrete Structure by Gamma Radiation

R. E. Rexroad, M. A. Schmoke H. J. Tiller, A. Foderaro, L. Degelman, G. Kowal

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 66-79

Technical Paper / dx.doi.org/10.13182/NSE64-A19276

Ratio of Capture to Fission in U²³⁵ at keV Neutron Energies

L. W. Weston, G. de Saussure, R. Gwin

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 80-87

Technical Paper / dx.doi.org/10.13182/NSE64-A19277

The Milne Problem in a Finite Domain I: Isotropic Scattering

F. A. Hinchey, E. A. Dean, J. B. Pearce

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 88-92

Technical Paper / dx.doi.org/10.13182/NSE64-A19278

Transport-Theory Calculations of Temperature Coefficients in Heterogeneous Reactor Lattices

John E. Suich, Henry C. Honeck

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 93-110

Technical Paper / dx.doi.org/10.13182/NSE64-A19279

Number 2

Table of Contents
Coated-Particle Fuel Symposium—Introduction
Total Neutron Cross Section of Pa²³³ from 0.01 to 1.0 eV(F. B. Simpson, J. W. Codding, J. R. Berreth)
Inelastic Neutron Scattering By Some Hydrogenous Moderators(W. Gläser, K. H. Beckurts)
The Nordheim-Fuchs Excursion Model with Non-Linear Reactivity Feedback(B. Wolfe)
A Simple Method of Fitting SOFOCATE Thermal Constants for Highly Enriched Water Moderated Reactors(K. R. Teare)
Accelerators of Charged Particles(E. Creutz)
Uranium, Vol. 8, Metallurgy of the Rarer Metals(John M. Googin)
Progress in Nuclear Energy, Series IV, “Technology, Engineering and Safety,” Vol. 5(Fred Albaugh)
Operating Experience with Power Reactors(James E. Owens)

P_N Calculations

G. R. Dalton

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 131-137

Technical Paper / dx.doi.org/10.13182/NSE64-A28926

An Absolute Thermal-Neutron-Flux Standard

R. G. Cochran, D. E. Feltz, J. D. Randall, J. V. Walker

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 138-141

Technical Paper / dx.doi.org/10.13182/NSE64-A28927

Measurements of Conversion Ratio, Resonance Escape and Fast Fission as Student Experiments

D. A. Daavettila

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 142-150

Technical Paper / dx.doi.org/10.13182/NSE64-A28928

Properties of Ceramic-Coated Nuclear-Fuel Particles

J. M. Blocker, Jr., M. F. Browning, W. J. Wilson, V. M. Secrest, A. C. Secrest, R. B. Landrigan, J. H. Oxley

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 153-170

Technical Paper / dx.doi.org/10.13182/NSE64-A28930

Irradiation Studies of Ceramic-Coated Nuclear Fuel Particles

Charles W. Townley, Neil E. Miller, Robert L. Ritzman, Richard J. Burian

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 171-179

Technical Paper / dx.doi.org/10.13182/NSE64-A28931

Development of Fueled Graphite Containing Pyrolytic-Carbon-Coated Carbide Particles for Non-purged, Gas-Cooled Reactor Systems

F. L. Carlsen, Jr., E. S. Bomar, W. O. Harms

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 180-200

Technical Paper / dx.doi.org/10.13182/NSE64-A28932

Development and Utilization of Pyrolytic-Carbon-Coated Carbide Fuel for the High-Temperature Gas-Cooled Reactor

Walter V. Goeddel

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 201-218

Technical Paper / dx.doi.org/10.13182/NSE64-A28933

Duplex Carbon-Coated Fuel Particles

R. A. Reuter

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 219-226

Technical Paper / dx.doi.org/10.13182/NSE64-A28934

The Development of Spherical Pyrolytic-Carbon-Coated UC₂ and UThC₂ Fuel Particles

H. G. Sowman, R. L. Surver, J. R. Johnson

Nuclear Science and Engineering / Volume 20 / Number 2 / October 1964 / Pages 227-234

Technical Paper / dx.doi.org/10.13182/NSE64-A28935

Number 3

Table of Contents
A Note on Delayed-Neutron Effects in Pulsed-Neutron Measurements on Multiplying Assemblies(C. Sastre and E. V. Weinstock)
Synergism in the Solvent Extraction of Alkali Metals(L. A. Bray)
Nuclear Engineering Fundamentals(Glen J. Schoessow)
Radioactive Isotopes in Instrumentation and Control(Ernest H. Wakefield)
Desalination of Water Using Conventional and Nuclear Energy(R. Philip Hammond)
High Sensitivity Counting Techniques(Serge A. Korff)
The Analytical Chemistry of Thorium(J. C. White)
Exterminator(Tom B. Fowler, Melvin Tobias and David R. Vondy, A. J. Vigilotti)

A Fluid-Bed Process for the Direct Conversion of Uranium Hexafluoride to Uranium Dioxide

I. E. Knudsen, H. E. Hootman and N. M. Levitz

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 259-265

Technical Paper / dx.doi.org/10.13182/NSE64-A19567

Material Buckling and Critical Masses of Uranium Rods Containing 3 wt % U²³⁵ in H₂0

W. B. Rogers, Jr. and F. E. Kinard

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 266-271

Technical Paper / dx.doi.org/10.13182/NSE64-A19568

Fast-Spectrum Doppler Measurements - Part II: A Measurement of a Negative Doppler Effect in U²³⁵ and New Measurements in Th²³² and U²³⁸

T. H. Springer, S. G. Carpenter and R. J. Tuttle

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 272-280

Technical Paper / dx.doi.org/10.13182/NSE64-A19569

Fast-Neutron Spectroscopy in a Pool-Type Reactor with Activation Detectors

G. Ben-David, E. Nardi and M. Pasternak

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 281-289

Technical Paper / dx.doi.org/10.13182/NSE64-A19570

A Simple, Compact Rod Drive Using a Stepping Motor

Edward F. Groh and Charles E. Cohn

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 290-297

Technical Paper / dx.doi.org/10.13182/NSE64-A19571

Neutron-Capture Cross Section of 35-h Rh¹⁰⁵

L. E. Glendenin and R. A. Schmitt

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 298-301

Technical Paper / dx.doi.org/10.13182/NSE64-A19572

Thermal-Neutron Capture Cross Section and Resonance Capture Integral of Ce¹⁴⁰ and Effective Capture Cross Section of Ce¹⁴¹

P. M. Lantz, C. R. Baldock and L. E. Idom

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 302-306

Technical Paper / dx.doi.org/10.13182/NSE64-A19573

Application of a Simple, Practical Method for Computing Interaction to Arrays Found Experimentally to be Critical

Hugh K. Clark

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 307-313

Technical Paper / dx.doi.org/10.13182/NSE64-A19574

Thermal-Neutron Transmission Through Plane Cadmium Covers

J. A. DeJuren and R. K. Paschall

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 314-317

Technical Paper / dx.doi.org/10.13182/NSE64-A19575

Optimum Reactor Shutdown Program for Minimum Xenon Buildup

Zoltan R. Rosztoczy and Lynn E. Weaver

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 318-323

Technical Paper / dx.doi.org/10.13182/NSE64-A19576

The Even-Order Spherical-Harmonics Method in Cylindrical Geometry

John O. Mingle

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 324-330

Technical Paper / dx.doi.org/10.13182/NSE64-A19577

Intermediate Resonance Absorption in Nonhomogeneous Systems

Rubin Goldstein and Harvey Brooks

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 331-337

Technical Paper / dx.doi.org/10.13182/NSE64-A19578

The Application of Inhour Modes to the Description of Non-Separable Reactor Transients

A. F. Henry

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 338-351

Technical Paper / dx.doi.org/10.13182/NSE64-A19579

Non-l/ν Thermalization Parameters for the Mass-1 and Nelkin Scattering Kernels

Gerald P. Calame

Nuclear Science and Engineering / Volume 20 / Number 3 / November 1964 / Pages 352-357

Technical Paper / dx.doi.org/10.13182/NSE64-A19580

Number 4

Table of Contents
On The Evaluation of Doppler-Broadened Cross-Section Functions(Alex Reichel)
The Alpha and Gamma Radiolysis of Biphenyl(W. H. Baldwin, P. S. Rudolph)
Nuclear Chemistry and Its Applications(Richard H. Wiswall, Jr.)
Russian-English Physics Dictionary(John Turkevich)
The Nuclear Reactor(Samuel Untermyer II)
Man-Made Transuranium Elements(Warren C. Johnson)
Pressure Vessel Design: Nuclear and Chemical Applications(Thomas Jaeger)
GRAD SQUARE(G. R. Dalton)
Error Propagation in Hot-Spot, Hot-Channel Analysis(Fred H. Tingey)

Detection of Gunpowder Residues by Neutron Activation Analysis

R. R. Ruch, V. P. Guinn, R. H. Pinker

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 381-385

Technical Paper / dx.doi.org/10.13182/NSE64-A20980

Measurement of Free Fission-Gas Pressure in Operating UO₂-Filled Fuel Rods

Myron B. Reynolds

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 386-391

Technical Paper / dx.doi.org/10.13182/NSE64-A20981

A Space-Dependent Dynamic Analysis of Boiling Water Reactor Systems

Amir N. Nahavandi, Richard F. von Hollen

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 392-413

Technical Paper / dx.doi.org/10.13182/NSE64-A20982

Thermal-Neutron Space-Time Decay Constants in Various Order P_N Approximations

A. Travelli, Gerald P. Calame

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 414-427

Technical Paper / dx.doi.org/10.13182/NSE64-A20983

Time-Dependent Flux in Small Assemblies

F. D. Judge, P. B. Daitch

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 428-435

Technical Paper / dx.doi.org/10.13182/NSE64-A20984

The Age of Fission Neutrons to Indium-Resonance Energy in Water

R. K. Paschall

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 436-444

Technical Paper / dx.doi.org/10.13182/NSE64-A20985

The Age of Fission Neutrons to Indium-Resonance Energy in Graphite

R. W. Campbell, R. K. Paschall, V. A. Swanson

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 445-454

Technical Paper / dx.doi.org/10.13182/NSE64-A20986

A Thermal Neutron Extrapolation Length Measurement

Edward E. Carroll, Jr., Robert W. Stooksberry

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 455-461

Technical Paper / dx.doi.org/10.13182/NSE64-A20987

Transport Solution of the One-Speed Slab Albedo Problem

N. J. McCormick, M. R. Mendelson

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 462-467

Technical Paper / dx.doi.org/10.13182/NSE64-A20988

A Double-Iteration Method for Determination of Diffusion Length

Richard E. Kaiser, William R. Kimel

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 468-475

Technical Paper / dx.doi.org/10.13182/NSE64-A20989

A Determination of the Cadmium Absorption of Resonance Neutrons in Cadmium-Covered Indium Foils

J. E. Powell, J. V. Walker

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 476-480

Technical Paper / dx.doi.org/10.13182/NSE64-A20990

The Effect of Flux Anisotropy on Neutron-Detector Foils

G. R. Dalton, R. K. Osborn

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 481-492

Technical Paper / dx.doi.org/10.13182/NSE64-A20991

Limitations in the Orthonormal Expansion of Neutron Spectra with Activation Measurements

Raymond Gold

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 493-512

Technical Paper / dx.doi.org/10.13182/NSE64-A20992

Anisotropic Scattering in the S_N Method

P. F. Zweifel, S. B. Garg

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 513-516

Technical Paper / dx.doi.org/10.13182/NSE64-A20993

Time-Dependent Variational Principles for Nonconservative Systems

Jeffrey Lewins

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 517-520

Technical Paper / dx.doi.org/10.13182/NSE64-A20994

Wear Rates in Automotive Engines by Liquid Scintillation Counting of Fe⁵⁵

H. H. Ross, R. P. Gardner, J. W. Dunn, III

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 521-526

Technical Paper / dx.doi.org/10.13182/NSE64-A20995

of U²³⁸ from 1.5 to 15 MeV

I. Asplund-Nilsson, H. Condé, N. Starfelt

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 527-535

Technical Paper / dx.doi.org/10.13182/NSE64-A20996

Radiation and Creep Analysis for Strain Stress Distributions in Tubular Fuel Elements

Benjamin M. Ma, Glenn Murphy

Nuclear Science and Engineering / Volume 20 / Number 4 / December 1964 / Pages 536-546

Technical Paper / dx.doi.org/10.13182/NSE64-A20997