Home / Publications / Journals / Nuclear Science and Engineering / Volume 8

Volume 8

Number 1

Table of Contents
Hydrogen Movement in Zircaloy-2 Under Thermal Gradients(C. N. Spalaris, A. E. Pickett, G. G. Gaul)
Breeding Potential of Thermal Reactors(J. F. Kaufmann, E. D. Jordan)
Measurements of the Temperature Dependence of Thermal Neutron Diffusion Parameters in Water and Dowtherm A(M. Küchle)

Few Group Analysis of D₂O-U²³⁵ Assemblies

Charles N. Kelber, Philip Kier

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE8-1-1

The Effect of a Diagonal Control Rod in a Cylindrical Reactor

T. Nilsson, N. G. Sjöstrand

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 12-13

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Development Testing of Liquid Metal and Molten Salt Heat Exchangers

R. E. MacPherson, J. C. Amos, H. W. Savage

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 14-20

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Design Precepts for High-Temperature Heat Exchangers

A. P. Fraas

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 21-31

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Evaluation of the Performance of Liquid Metal and Molten Salt Heat Exchangers

M. M. Yarosh

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 32-43

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A New Method for the Solution of Group Diffusion Equations

A. Foderaro, H. L. Garabedian

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 44-52

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The Rice Formulation of Pile Noise

Edgar F. Bennett

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 53-61

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Measurements on the Diffusion Length of Thermal Neutrons in Water from 25 to 296°C

K. S. Rockey, W. Skolnik

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 62-65

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Evaluation of Low-Energy Cross Section Data for U²³³

J. E. Evans, R. G. Fluharty

Nuclear Science and Engineering / Volume 8 / Number 1 / July 1960 / Pages 66-82

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Number 2

Table of Contents
Greuling-Goertzel Approximation in Muft IV Code(E. M. Gelbard)
Age of U²³³ Fission Neutrons in Water(W. G. Pettus)
Scattering of Thermal Neutrons in Graphite(P. G. Khubchandani)

A Study of Nonlinear Reactor Dynamics

A. Z. Akcasu, A. Dalfes

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 89-94

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Variational Representations in Reactor Physics Derived from a Physical Principle

Jeffery Lewins

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 95-104

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Techniques for the Irradiation of Ceramic Fuels in a Moderate Thermal Neutron Flux

William G. Blessing

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 105-111

Technical Paper / dx.doi.org/10.13182/NSE60-A25785

Thermal Neutron Cross-Section Measurements of U²³³, U²³⁵, Pu²⁴⁰, U²³⁴, and I¹²⁹ with the ORNL Fast Chopper Time-of-Flight Neutron Spectrometer

R. C. Block, G. G. Slaughter, J. A. Harvey

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 112-121

Technical Paper / dx.doi.org/10.13182/NSE60-A25786

Some Monte Carlo and Analytical Results for Resonance Capture in Lattices

Wolfgang Rothenstein

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 122-127

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The Stability of “Stable” Fission-Product Poisoning

S. B. Gunst, J. C. Connor, E. Fast

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 128-132

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Reactions Between Steel Surfaces and Zirconium in Liquid Bismuth

John R. Weeks, Carl J. Klamut

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 133-147

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Age of Na—Be Neutrons in Water and Kerosene

D. Graham Foster, Jr.

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 148-156

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Time-Dependent Neutron Spectra

Juan Koppel

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 157-163

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A Numerical Technique for Solving Group Diffusion Equations

Eugene L. Wachspress

Nuclear Science and Engineering / Volume 8 / Number 2 / August 1960 / Pages 164-170

Technical Paper / dx.doi.org/10.13182/NSE60-A25792

Number 3

Table of Contents
Development of Flow in a Loop after Pumping Startup(David Burgreen)
Spatial Distribution of Resonance Absorption in Fuel Elements(Manfred Wagner)
A Note on the Perturbation Method in Neutron Transport Theory(G. Rakavy)
Methods and Cross Sections for Calculating the Fast Effect

Gamma Radiation from Inelastic Scattering of 14-Mev Neutrons by the Common Earth Elements

Richard L. Caldwell, William R. Mills, Jr., John B. Hickman, Jr.

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 173-182

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Low-Energy Neutron Resonances in Erbium and Gadolinium

H. Bjerrum Møller, F. J. Shore, V. L. Sailor

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 183-192

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The Distribution of Thermal Neutrons in Space and Energy in Reactor Lattices. Part I: Theory

Henry C. Honeck

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 193-202

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The Distribution of Thermal Neutrons in Space and Energy in Reactor Lattices. Part II: Comparison of Theory and Experiment

Henry C. Honeck, Irving Kaplan

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 203-209

Technical Paper / dx.doi.org/10.13182/NSE60-A25800

Manganese Bath Measurements of _η of U²³³ and U²³⁵

R. L. Macklin, G. Desaussure, J. D. Kington, W. S. Lyon

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 210-220

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Critical Measurements on Near-Homogeneous BeO—Moderated, Enriched-Uranium Fueled Systems

Fred A. Kloverstrom, Richard M. R. Deck, Arnold J. Reyenga

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 221-225

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Criticality Calculations of BeO—Moderated Enriched Uranium Systems

Richard E. Lingenfelter

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 226-232

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The Dynamics of a Xenon-Controlled Reactor

J. Chernick

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 233-243

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Effect of Delayed Neutrons on Nonlinear Reactor Stability

Elias P. Gyftopoulos, Jacques Devooght

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 244-250

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On the Applicability of the Transport Approximation to the Calculation of Reactivity

G. Rakavy

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 251-253

Technical Paper / dx.doi.org/10.13182/NSE60-A25806

Control Rod Theory for Asymmetrical Arrays and Reflected Cores

Raymond L. Murray, William T. Price, Samuel H. Birken

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 254-259

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Thermal Neutron Flux Distributions in Metal-Hydrogenous Shields

D. C. Anderson, K. Shure

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 260-269

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Standard Boron Solutions for Neutron Absorption Measurements

S. Wexler

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 270-273

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The Engineering Aspects of the Water Vapor Permeability of Glove Materials

J. E. Ayer, R. M. Mayfield, D. R. Schmitt

Nuclear Science and Engineering / Volume 8 / Number 3 / September 1960 / Pages 274-276

Technical Paper / dx.doi.org/10.13182/NSE60-A25810

Number 4

Table of Contents
The Dancoff Effect in H₂O-D₂O Moderated Lattices(W. G. Pettis)
The Surface Tensions of Liquid Metals at Their Melting Points(Simon W. Strauss)
Generalized Resonance Integral Representation(Melvin M. Levine)
Breeder Economics(Jack Chernick)
International Control of Nuclear Maritime Activities(Louis H. Roddis, Jr.)
L'Electronique Nucléaire—Nuclear Electronics(Alain L. Colomb)
Radiations and Matter(R. B. Murray)
The Isotope Index, The Complete Guide to the Isotopes(Marshall Brucer, M. D.)
International Directory of Radioisotopes(Marshall Brucer, M. D.)

Plutonium-Aluminum Solid Solubility and Diffusion Studies

Arthur E. Hall

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 283-288

Technical Paper / dx.doi.org/10.13182/NSE60-A28857

Photoneutrons and the Control of a Pool Type Reactor

A. L. Colomb

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 289-293

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Neutron Rethermalization Cross Section Measurements in Graphite

R. A. Bennett, R. E. Heineman

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 294-299

Technical Paper / dx.doi.org/10.13182/NSE60-A28859

Thermal Neutron Flux Depression by Absorbing Foils

R. H. Ritchie, H. B. Eldridge

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 300-311

Technical Paper / dx.doi.org/10.13182/NSE60-A28860

An Apparatus for Measurement of the Surface Area of Irradiated Coarse Powders

F. D. Leipziger, L. A. Altamari

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 312-314

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Dynamic Programming and Nuclear Reactor Systems Design

Nicholas Kallay

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 315-325

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The Internal Feedback of EBR-I Mark III

J. C. Carter, D. W. Sparks, J. H. Tesster

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 326-339

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Temperature Control of Fueled Irradiation Capsules by Variable Conductance

W. W. Godsin

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 340-345

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Some Aspects of Fluid Fuel Reactor Development

Alvin M. Weinberg

Nuclear Science and Engineering / Volume 8 / Number 4 / October 1960 / Pages 346-360

Technical Paper / dx.doi.org/10.13182/NSE60-A28865

Number 5

Table of Contents
Reactivity Coefficients of Rare Earth Oxides(J. Harry Mortenson, Russell M. Ball)
Comparison of Measurements with a Monte Carlo Calculated Spatial Distribution of Resonance Neutron Capture in a Uranium Rod(G. Smith, J. Hardy Jr., D. Klein)
Some Series Occurring in the Theory of the Square Lattice Cell(D. C. Leslie)

Investigation of Natural Convection Heat Transfer in Liquid Sodium

John S. McDonald, T. J. Connolly

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 369-377

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Reactor Neutron Activation Cross Sections for a Number of Elements

W. S. Lyon

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 378-380

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Water-Moderated Cores with Boron Steel Septa at Elevated Temperatures

G. D. Hickman, J. A. Bistline, L. A. MacNaughton

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 381-392

Technical Paper / dx.doi.org/10.13182/NSE60-A25818

Competitive Extinction in Neutron Monochromating Crystals

R. R. Spencer, J. R. Smith

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 393-399

Technical Paper / dx.doi.org/10.13182/NSE60-A25819

A Few-Group Theory of Water Gap Peaking

Gerald P. Calame

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 400-404

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Measurements of Pu and U²³⁵ Fission Rates in Water—Uranium Reactor Spectra

D. Klein

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 405-409

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A Nondestructive Assay Device for Highly Enriched Fuel Assemblies

Richard V. Babcock, Stanley L. Ruby

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 410-415

Technical Paper / dx.doi.org/10.13182/NSE60-A25822

An Experimental Study of the Relative U²³⁵ Fission Activation as a Function of Energy in Slightly Enriched Uranium-Water Lattices

John J. Volpe, D. Klein

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 416-425

Technical Paper / dx.doi.org/10.13182/NSE60-A25823

Thermal Neutron Flux Distributions in Space and Energy

Paul Michael

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 426-431

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Recovery of Uranium and Thorium from Graphite Fuel Elements. I. Grind-Leach Process

Mildred J. Bradley, Leslie M. Ferris

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 432-436

Technical Paper / dx.doi.org/10.13182/NSE60-A25825

Integral Reactor Theory: Orthogonality and Importance

M. A. Robkin, M. Clark, Jr.

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 437-442

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The Measurement of Reactivity

Cesar A. Sastre

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 443-447

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Number 6

Table of Contents
An H₂O-D₂O Moderated Reactor(W. P. Bebbington)
Delayed-Neutron-Groups Number Reduction(A. Kirchenmayer)

Long Wavelength Crystal Spectrometer and the Neutron Absorption Cross Sections of Gold and Boron

F. T. Gould, T. I. Taylor, W. W. Havens, Jr., B. M. Rustad, E. Melkonian

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 453-466

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Two Years of HRE-2 Operation

Paul N. Haubenreich

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 467-479

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The Application of Statistical Methods of Analysis for Predicting Burnout Heat Flux

R. T. Jacobs, J. A. Merrill

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 480-496

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The Temperature Coefficient of the Resonance Integral for Uranium Metal and Oxide

E. Hellstrand, P. Blomberg, S. Hörner

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 497-506

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Solvent Extraction Recovery of Technetium, Neptunium, and Uranium from Fluorination Plant Residues

C. F. Coleman, F. A. Kappelmann, B. Weaver

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 507-514

Technical Paper / dx.doi.org/10.13182/NSE60-A25836

Prompt Critical Assembly Gamma Ray Sources

Charles S. Shapiro

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 515-517

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Negative-Reactivity Measurements

William S. Hogan

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 518-522

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Fast-Neutron Critical Assemblies and Related Topics

H. C. Paxton

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Page 523

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Two Plutonium-Metal Critical Assemblies

G. A. Jarvis, G. A. Linenberger, J. D. Orndoff, H. C. Paxton

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 525-531

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Perturbation Theory of Reactivity Coefficients for Fast-Neutron Critical Systems

Gordon E. Hansen, Clifford Maier

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 532-542

Technical Paper / dx.doi.org/10.13182/NSE60-A25841

Reactivity Contributions of Various Materials in Topsy, Godiva, and Jezebel

L. B. Engle, G. E. Hansen, H. C. Paxton

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 543-569

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Critical Plutonium and Enriched-Uranium-Metal Cylinders of Extreme Shape

G. E. Hansen, H. C. Paxton, D. P. Wood

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 570-577

Technical Paper / dx.doi.org/10.13182/NSE60-A25843

Critical Masses of Cylinders of Plutonium Diluted with Other Metals

D. P. Wood, C. C. Byers, L. C. Osborn

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 578-587

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Critical Masses of Enriched-Uranium Cylinders with Multiple Reflectors of Medium-Z Elements

G. E. Hansen, D. P. Wood, W. U. Geer

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 588-594

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Leakage Neutron Spectrum from a Bare Pu²³⁹ Critical Assembly

Leona Stewart

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 595-597

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Spectral Comparisons with High Energy Activation Detectors

James Grundl, Arthur Usner

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 598-607

Technical Paper / dx.doi.org/10.13182/NSE60-A25847

Cross Sections of Various Materials in the Godiva and Jezebel Critical Assemblies

Cleo C. Byers

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 608-614

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Critical Reflector Thicknesses for Spherical U²³³ and Pu²³⁹ Systems

E. A. Plassmann, D. P. Wood

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 615-620

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Computational Survey of Idealized Fast Breeder Reactors

William H. Roach

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 621-651

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A Uranium-Metal Exponential Experiment

Curtis G. Chezem

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 652-669

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General Solution of the Reactor Kinetic Equations

G. R. Keepin, C. W. Cox

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 670-690

Technical Paper / dx.doi.org/10.13182/NSE60-A25852

Godiva II—An Unmoderated Pulse-Irradiation Reactor

T. F. Wimett, R. H. White, W. R. Stratton, D. P. Wood

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 691-708

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Assembly of Fissionable Material in the Presence of a Weak Neutron Source

G. E. Hansen

Nuclear Science and Engineering / Volume 8 / Number 6 / December 1960 / Pages 709-719

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