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Number 1
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Number 4
Number 5
Number 6

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 | 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
Technical Paper | doi.org/10.13182/NSE8-1-12
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
Technical Paper | doi.org/10.13182/NSE8-1-14
Design Precepts for High-Temperature Heat Exchangers
A. P. Fraas
Nuclear Science and Engineering | Volume 8 | Number 1 | July 1960 | Pages 21-31
Technical Paper | doi.org/10.13182/NSE8-1-21
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
Technical Paper | doi.org/10.13182/NSE8-1-32
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
Technical Paper | doi.org/10.13182/NSE8-1-44
The Rice Formulation of Pile Noise
Edgar F. Bennett
Nuclear Science and Engineering | Volume 8 | Number 1 | July 1960 | Pages 53-61
Technical Paper | doi.org/10.13182/NSE8-1-53
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
Technical Paper | doi.org/10.13182/NSE8-1-62
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
Technical Paper | doi.org/10.13182/NSE8-1-66

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
Technical Paper | doi.org/10.13182/NSE60-A25783
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
Technical Paper | doi.org/10.13182/NSE60-A25784
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 | 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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25787
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
Technical Paper | doi.org/10.13182/NSE60-A25788
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
Technical Paper | doi.org/10.13182/NSE60-A25789
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
Technical Paper | doi.org/10.13182/NSE60-A25790
Time-Dependent Neutron Spectra
Juan Koppel
Nuclear Science and Engineering | Volume 8 | Number 2 | August 1960 | Pages 157-163
Technical Paper | doi.org/10.13182/NSE60-A25791
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25797
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
Technical Paper | doi.org/10.13182/NSE60-1
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
Technical Paper | doi.org/10.13182/NSE60-A25799
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25801
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
Technical Paper | doi.org/10.13182/NSE60-A25802
Criticality Calculations of BeO—Moderated Enriched Uranium Systems
Richard E. Lingenfelter
Nuclear Science and Engineering | Volume 8 | Number 3 | September 1960 | Pages 226-232
Technical Paper | doi.org/10.13182/NSE60-A25803
The Dynamics of a Xenon-Controlled Reactor
J. Chernick
Nuclear Science and Engineering | Volume 8 | Number 3 | September 1960 | Pages 233-243
Technical Paper | doi.org/10.13182/NSE60-A25804
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
Technical Paper | doi.org/10.13182/NSE60-A25805
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25807
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
Technical Paper | doi.org/10.13182/NSE60-A25808
Standard Boron Solutions for Neutron Absorption Measurements
S. Wexler
Nuclear Science and Engineering | Volume 8 | Number 3 | September 1960 | Pages 270-273
Technical Paper | doi.org/10.13182/NSE60-A25809
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 | 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 | 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
Technical Paper | doi.org/10.13182/NSE60-A28858
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 | 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 | 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
Technical Paper | doi.org/10.13182/NSE60-A28861
Dynamic Programming and Nuclear Reactor Systems Design
Nicholas Kallay
Nuclear Science and Engineering | Volume 8 | Number 4 | October 1960 | Pages 315-325
Technical Paper | doi.org/10.13182/NSE60-A28862
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
Technical Paper | doi.org/10.13182/NSE60-A28863
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
Technical Paper | doi.org/10.13182/NSE60-A28864
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25816
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
Technical Paper | doi.org/10.13182/NSE60-A25817
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 | 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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25820
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
Technical Paper | doi.org/10.13182/NSE60-A25821
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 | 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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25824
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25826
The Measurement of Reactivity
Cesar A. Sastre
Nuclear Science and Engineering | Volume 8 | Number 5 | November 1960 | Pages 443-447
Technical Paper | doi.org/10.13182/NSE60-A25827

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
Technical Paper | doi.org/10.13182/NSE60-A25832
Two Years of HRE-2 Operation
Paul N. Haubenreich
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 467-479
Technical Paper | doi.org/10.13182/NSE60-A25833
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
Technical Paper | doi.org/10.13182/NSE60-A25834
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
Technical Paper | doi.org/10.13182/NSE60-A25835
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25837
Negative-Reactivity Measurements
William S. Hogan
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 518-522
Technical Paper | doi.org/10.13182/NSE60-A25838
Fast-Neutron Critical Assemblies and Related Topics
H. C. Paxton
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Page 523
Technical Paper | doi.org/10.13182/NSE60-A25839
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
Technical Paper | doi.org/10.13182/NSE60-A25840
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25842
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25844
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
Technical Paper | doi.org/10.13182/NSE60-A25845
Leakage Neutron Spectrum from a Bare Pu²³⁹ Critical Assembly
Leona Stewart
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 595-597
Technical Paper | doi.org/10.13182/NSE60-A25846
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 | 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
Technical Paper | doi.org/10.13182/NSE60-A25848
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
Technical Paper | doi.org/10.13182/NSE60-A25849
Computational Survey of Idealized Fast Breeder Reactors
William H. Roach
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 621-651
Technical Paper | doi.org/10.13182/NSE60-A25850
A Uranium-Metal Exponential Experiment
Curtis G. Chezem
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 652-669
Technical Paper | doi.org/10.13182/NSE60-A25851
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 | 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
Technical Paper | doi.org/10.13182/NSE60-2
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
Technical Paper | doi.org/10.13182/NSE60-3