Home / Publications / Journals / Nuclear Science and Engineering / Volume 11

Volume 11

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE61-A26046