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Number 1
Number 2

Number 3
Number 4

Number 1

Table of Contents
Criticality of Low Enrichment U²³⁵ in Hydrogen (John Mihalczo)
On the General Solution of the Reactor Kinetic Equations (Jeffery Lewins)
Observations on Uranium Oxide Single Crystals (L. L. Colombo, J. C. Danko, H. M. Ferrari)
Power Reactor Technology (W. Kenneth Davis)
Directory of Nuclear Reactors. Vol. III. Research, Test and Experimental Reactors (Lawrence C. Widdoes)

Void Measurement in a Boiling Reactor
J. A. Thie, J. Beidelman, B. Hoglund
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 1-6
Technical Paper | doi.org/10.13182/NSE61-A25977
Neutron Thermalization in Plane Lattices
Jacques Devooght
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 7-18
Technical Paper | doi.org/10.13182/NSE61-A25978
Application of Ion Exchange for Control of Nuclear Rocket Reactors
Chuk-Ching Ma
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 19-25
Technical Paper | doi.org/10.13182/NSE61-A25979
Efficiency of Cylindrical Control Rods Partially Inserted in a Bare Reactor
J. Ligou
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 26-38
Technical Paper | doi.org/10.13182/NSE61-A25980
Some Remarks on the Effect of a Nonuniform Temperature Distribution on the Temperature Dependence of Resonance Absorption
Lawrence Dresner
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 39-42
Technical Paper | doi.org/10.13182/NSE61-A25981
Multigroup Diffusion with Periodic Arrays of Line Sources
Frank B. Estabrook
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 43-47
Technical Paper | doi.org/10.13182/NSE61-A25982
The Measurement of the Surface Area of Uranium Dioxide Powder
Pietro R. Gorla
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 48-54
Technical Paper | doi.org/10.13182/NSE61-A25983
General Stability Criteria for Nuclear Reactor with Two Feedback Paths of Single Time Constant
J. Miida, N. Suda
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 55-60
Technical Paper | doi.org/10.13182/NSE61-A25984
An Approach to Reactor Physics Using Results of Integral Experiments—Part II
Karl H. Puechl
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 61-64
Technical Paper | doi.org/10.13182/NSE61-A25985
A Precision Measurement of the Total Cross Section of Pu²³⁹ between 0.00291 and 0.1 ev
G. J. Safford, W. W. Havens, Jr.
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 65-68
Technical Paper | doi.org/10.13182/NSE61-A25986
The Elimination of Flux Perturbation Associated with Neutron Detecting Foils
J. D. Randall, J. V. Walker
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 69-73
Technical Paper | doi.org/10.13182/NSE61-A25987
Half-Lives of Radionuclides—II
E. I. Wyatt, S. A. Reynolds, T. H. Handley, W. S. Lyon, H. A. Parker
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 74-75
Technical Paper | doi.org/10.13182/NSE61-A25988
Open Loop Stability and Response of Nuclear Rocket Engines
Harold P. Smith, Jr., Alan H. Stenning
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 76-84
Technical Paper | doi.org/10.13182/NSE61-A25989
Disadvantage Factors in Slab Geometry by the P₂ Calculation
John O. Mingle
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 85-89
Technical Paper | doi.org/10.13182/NSE61-A25990
Separation of Transplutonium and Rare Earth Elements by Liquid—Liquid Extraction
R. D. Baybarz, R. E. Leuze
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 90-94
Technical Paper | doi.org/10.13182/NSE61-A25991

Number 2

Table of Contents
Re: Solid State Electrolysis in Yttrium Metal (Frank Kerze, Jr.)
A Generalized Equivalence Theorem For Resonance Escape in Heterogeneous Systems (Bertram Wolfe)
The Effect of Bragg Cutoff on the Diffusion of Thermal Neutrons in a Semi-Infinite Slab of Beryllium (R. D. Jain, S. V. Lawande)
Nuclear Reactor Materials (Frank Kerze, Jr.)
Nuclear Propulsion (Lawrence Dresner)
Heavy Water Lattices (D. S. St. John)
Elements of Nuclear Engineering (T. F. Parkinson)
Thermal Reactor Theory (Alvin M. Weinberg)
Basic Principles of Fission Reactors (Karl H. Puechl)
Elementary Nuclear Physics (Raymond L. Murray)
Materials for Nuclear Engineers (E. Creutz)
Radioisotope Laboratory Techniques (Abraham S. Goldin)
Nuclear Reactor Optimization (H. D. Brown)

Fuel Programming in Pool-Type Research Reactors of Intermediate Power Level
Ernest E. Hill, Frederick J. Shon
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 105-110
Technical Paper | doi.org/10.13182/NSE61-A28053
Low Energy Total Neutron Cross Section of Pu-241
O. D. Simpson, R. P. Schuman
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 111-115
Technical Paper | doi.org/10.13182/NSE61-A28054
Milne's Problem for Thermal Neutrons in a Nonabsorbing Medium
R. Kladnik, I. Kuscher
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 116-120
Technical Paper | doi.org/10.13182/NSE61-A28055
Some Theoretical Aspects of Vapor Void Formation in Heated Vertical Channels
Gerald Houghton
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 121-128
Technical Paper | doi.org/10.13182/NSE61-A28056
Neutron Age Measurements in Metal-Water Lattices
William G. Pettus
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 129-132
Technical Paper | doi.org/10.13182/NSE61-A28057
The Effect of Burnable Fission Products in Power Reactor Kinetics
Henri B. Smets
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 133-141
Technical Paper | doi.org/10.13182/NSE61-A28058
Logarithmic Rate Meters and Period Meters: A Theoretical Study of Noise and Transient Response
A. G. Klein
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 142-153
Technical Paper | doi.org/10.13182/NSE61-A28059
Irradiation Effects in Dispersions
Donald L. Keller, Lewis E. Hulbert, Bruce W. Dunnington
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 154-158
Technical Paper | doi.org/10.13182/NSE61-A28060
A Crosscorrelation Method for Measuring the Impulse Response of Reactor Systems
J. Douglas Balcomb, Howard B. Demuth, Elias P. Gyftopoulos
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 159-166
Technical Paper | doi.org/10.13182/NSE61-A28061
The Analysis of Foil Activation Experiments in Infinite Homogeneous Media
Harvey J. Amster, Robert C. Gast
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 167-178
Technical Paper | doi.org/10.13182/NSE61-A28062
Spatial Distribution in Water at Indium Resonance of Neutrons from a 1.4 Mev D-D Source
J. A. de Juren, M. Reier, R. W. Stooksberry
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 179-191
Technical Paper | doi.org/10.13182/NSE61-A28063
Analysis of a Foil Activation Experiment for a D-D Neutron Source in Water
Harvey J. Amster, Robert C. Gast
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 192-198
Technical Paper | doi.org/10.13182/NSE61-A28064
Prompt Neutron Decay Constants in Multiplying Hydrogenous Media
D. R. Bach, S. I. Bunch, R. J. Cerbone, R. E. Slovacek
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 199-210
Technical Paper | doi.org/10.13182/NSE61-A28065
Effect of Bragg Cutoff on the Diffusion of Thermal Neutrons in a Finite Solid Medium
S. Sanatani, L. S. Kothari
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 211-217
Technical Paper | doi.org/10.13182/NSE61-A28066
Isotopic and Scavenger Evidence for Radiolysis Mechanisms in Aromatic Hydrocarbons
John G. Burr, J. M. Scarborough, J. D. Strong, R. I. Akawie, R. A. Meyer
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 218-226
Technical Paper | doi.org/10.13182/NSE61-A28067

Number 3

Table of Contents
The Depression of Thermal Neutron Flux and Density by Absorbing Foils (G. C. Hanna)
Ratio of Fundamental and Second Order Harmonics in Flux for Oscillator Experiments with Varying Amplitude of Reactivity Insertion (Henry A. Sandmeier)
Simplified Calculation on Thermal Transient of a UO₂ Fuel Rod (L. S. Tong)
A Differential Equation for Calculating Doppler Broadened Resonances (Harvey J. Amster)
Crystal Spectrometer Measurement of the MITR Thermal Neutron Spectrum (Robert I. Schermer, Gordon Brownell)
Total Cross Sections of Hydrocarbons and Tissue (Robert I. Schermer, Gordon Brownell)
Decay Schemes of Radioactive Nuclei (William H Sullivan)
Steam Cycles for Nuclear Power Plant (R. W. Dickinson)
Radiation Biophysics (Arthur C. Upton)
Nuclear Reactor Theory (Robert V. Meghreblian)
Fast Reactor Cross Sections (Harvey Amster)
Nuclear Reactor Stability (Walter C. Lipinski)
Handbook of Thermophysical Properties of Solid Materials, Vol. I—Elements (Melting Temperature Above 1000°F) (Robert I. Strough)
1960 Nuclear Data Tables. Part 1. Consistent Set of Energies Liberated in Nuclear Reactions Targets in the Mass Region A ≤ 66 (John R. Stehn)
1960 Nuclear Data Tables. Part 2. Consistent Set of Energies Liberated in Nuclear Reactions Targets in the Mass Region 67 ≤ A ≤ 199 (John R. Stehn)
Reactor Handbook, Vol. I: Materials (R. Carson Dalzell)
Nuclear Reactor Shielding (Phillip S. Mittelman)
APWRC-CELCOR (G. A. Cannon, T. M. Olsen, E. A. Schaefer)
WHIRLAWAY (T. B. Fowler, Melvin Tobias)
GAM-I (G. D. Joanou)
SLOP-I (E. Gelbard, H. Bohl)
ECESS (W. W. Clendenin)

Calculation of the Neutron Leakage Spectra and Neutron Doses from Bare Critical Systems
J. R. Knight
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 239-245
Technical Paper | doi.org/10.13182/NSE61-A25998
Interaction of Separated Fissionable Sysems. Part I
Floro Miraldi, Melville Clark, Jr.
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 246-255
Technical Paper | doi.org/10.13182/NSE61-A25999
Interaction of Separated Fissionable Systems. Part II
Floro Miraldi, Melville Clark, Jr.
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 256-262
Technical Paper | doi.org/10.13182/NSE61-A26000
Determination and Application of the Diffusion Coefficient for Hydrogen in Uranium at 800°C
C. J. Oblinger, H. A. Dube
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 263-266
Technical Paper | doi.org/10.13182/NSE61-A26001
Modified Zirflex Process for Dissolution of 1–10% U-Zr Alloy Fuels in Aqueous NH₄F-NH₄NO₃-H₂O₂
T. A. Gens, R. E. Blanco
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 267-273
Technical Paper | doi.org/10.13182/NSE61-A26002
Anion Exchange Separation of Trivalent Actinides and Lanthanides
M. H. Lloyd, R. E. Leuze
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 274-277
Technical Paper | doi.org/10.13182/NSE61-A26003
Chemical Feasibility of Nuclear Poisons in Uranium-Thorium Fuel Processing Systems
J. G. Moore, R. H. Rainey
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 278-284
Technical Paper | doi.org/10.13182/NSE61-A26004
The Solution of Many Region Reactor Kinetics Problems on an Analog Computer
C. N. Kelber, L. C. Just, N. F. Morehouse, Jr.
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 285-289
Technical Paper | doi.org/10.13182/NSE61-A26005
The Statistical Aspects of Nuclear Reactor Fuel Element Temperature
Frederick H. Abernathy
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 290-297
Technical Paper | doi.org/10.13182/NSE61-A26006
Total Slow Neutron Cross Section Measurements of Titanium, Zirconium, and Hafnium
E. G. Joki, J. E. Evans, R. R. Smith
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 298-303
Technical Paper | doi.org/10.13182/NSE61-A26007
A Void Measurement Technique for Local Boiling
H. C. Perkins, Jr., M. Yusuf, G. Leppert
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 304-311
Technical Paper | doi.org/10.13182/NSE61-A26008
Precision Measurements of the Neutron Total Cross Section of U²³⁵
A. Saplakoglu
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 312-317
Technical Paper | doi.org/10.13182/NSE61-A26009
Pneumatic Temperature Probes for Gas-Cooled Reactors
Lester L. Kintner, Donald A. Lampe, Aikman Armstrong
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 318-323
Technical Paper | doi.org/10.13182/NSE61-A26010
Irradiated Ra:Be Neutron Sources
D. J. Dudziak, L. B. Freeman
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 324-327
Technical Paper | doi.org/10.13182/NSE61-A26011
Method of Studying Xenon Spatial Instability with an Analog Computer
R. M. Pearce
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 328-337
Technical Paper | doi.org/10.13182/NSE61-A26012

Number 4

Table of Contents
Additional Exponential Representations of Gamma-Ray Build-Up Factors (G. L. STROBEL)
Re: “Thermal Neutron Flux Depression by Absorbing Foils” and “Flux Perturbations by Thermal Neutron Detectors” (R. H. RITCHIE, G. R. DALTON)
The Milne Problem with a Polynomial Source (T. AUERBACH)

The Thermal Utilization in a Rectangular Cell
A. PAZY, S. GOSHEN
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 357-361
Technical Paper | doi.org/10.13182/NSE61-A26036
Gamma Ray Streaming Through Two-Legged Rectangular Ducts
J. C. LEDOUX, A. B. CHILTON
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 362-368
Technical Paper | doi.org/10.13182/NSE61-A26037
Low Energy Neutron Cross Sections of Dy¹⁶⁴
R. SHER, S. TASSAN, E. V. WEINSTOCK, A. HELLSTEN
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 369-376
Technical Paper | doi.org/10.13182/NSE61-A26038
FUELCYC, a New Computer Code for Fuel Cycle Analysis: Part I. Computational Model
RAYMOND T. SHANSTROM, MANSON BENEDICT
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 377-385
Technical Paper | doi.org/10.13182/NSE61-A26039
FUELCYC, a New Computer Code for Fuel Cycle Analysis: Part II. Examples of Applications
MANSON BENEDICT, RAYMOND T. SHANSTROM, STANLEY L. AMBERG, N. BARRIE MCLEOD, PAUL T. STERANKA
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 386-396
Technical Paper | doi.org/10.13182/NSE61-A26040
Measurement of ν in Fast Neutron Fission of Th²³² and U²³⁸
H. CONDÉ, N. STARFELT
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 397-404
Technical Paper | doi.org/10.13182/NSE61-A26041
The Determination of the Period-Reactivity Relation and Open-Loop Reactor Transfer Function From Rod-Drop Decay Data
W. J. FADER, R. C. HARRISON
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 405-414
Technical Paper | doi.org/10.13182/NSE61-A26042
Neutron Transport with Anisotropic Scattering
Janusz R. Mika
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 415-427
Technical Paper | doi.org/10.13182/NSE61-1
On the Stability of Homogeneous Nuclear Reactors with Non-Linear Reactivity Dependence on Temperature
HENRI B. SMETS
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 428-433
Technical Paper | doi.org/10.13182/NSE61-A26044
Preparation and Fabrication of Plutonium Fuel Alloy for Los Alamos Molten Plutonium Reactor Experiment No.1
J. W. ANDERSON, W. D. MCNEESE, C. C. BURWELL, J. A. LEARY
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 434-440
Technical Paper | doi.org/10.13182/NSE61-A26045
A Discussion of the Correlation of Critical Conditions for Bare Homogeneous Reactors
BENJAMIN PINKEL, GEORGE B. W. YOUNG
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 441-449
Technical Paper | doi.org/10.13182/NSE61-A26046