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Volume 10

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Number 1

Table of Contents
On the Calculation of Water Gap Peaking(Gerald P. Calame)
Reactivity Effects of Protactinium-233 Buildup in U²³³ Fast Breeder Reactors(Arthur J. Goldman)
Re: The Application of Statistical Methods of Analysis for Predicting Burnout Heat Flux(W. R. Gambill)
Re: The Application of Statistical Methods of Analysis for Predicting Burnout Heat Flux—Rebuttal(R. T. Jacobs, J. A. Merrill)
Abstract No. 9(F. W. Brinkley, C. B. Mills)
Abstract No. 10(Melvin Tobias, T. B. Fowler)
Abstract No. 11(H. Rief)
SM-2 Flexible Critical Experiments
On the Solution of Transport Problems by Conditional Monte Carlo(D. W. Drawbaugh)

Calculations of the Neutron Age in Water and Heavy Water for D-D Sources

John W. Cooper

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE61-A25922

Age to Indium Resonance for D-D Neutrons in Heavy Water

V. Spiegel, Jr., A. C. B. Richardson

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 11-15

Technical Paper / dx.doi.org/10.13182/NSE61-A25923

Some Calculations on the Age of Neutrons in D₂O

Herbert Goldstein, Jeremiah Certaine

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 16-23

Technical Paper / dx.doi.org/10.13182/NSE61-A25924

Further Results of Irradiation of Uranium Carbide

A. W. Hare, S. Aifant, F. A. Rough, D. I. Slnizer

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 24-30

Technical Paper / dx.doi.org/10.13182/NSE61-A25925

A Two-Mode Variational Procedure for Calculating Thermal Diffusion Theory Parameters

G. P. Calame, F. D. Federighi, P. A. Ombrellaro

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 31-39

Technical Paper / dx.doi.org/10.13182/NSE61-A25926

Hydraulic Studies for the Fluid-Bed Reactor

V. P. Kelly

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 40-44

Technical Paper / dx.doi.org/10.13182/NSE61-A25927

Pulsed Neutron Measurement of Control Rod Worths

O. C. Kolar, F. A. Kloverstrom

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 45-52

Technical Paper / dx.doi.org/10.13182/NSE61-A25928

The Determination of Hydrogen in Uranium by Mass Spectrometry

L. A. Fergason, D. E. Seizinger, C. H. McBride

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 53-56

Technical Paper / dx.doi.org/10.13182/NSE61-A25929

U²³⁸ Epithermal Capture in PWR-1 Blanket Clusters

W. Baer

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 57-60

Technical Paper / dx.doi.org/10.13182/NSE61-A25930

Fast Neutron Energy Spectra in Graphite-Moderated Reactors

Mark T. Robinson, O. S. Oen, D. K. Holmes

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 61-69

Technical Paper / dx.doi.org/10.13182/NSE61-A25931

Determination of Trace Quantities of Fission Products in Nonirradiated Natural and Depleted Uranium Salts

P. K. Kuroda, M. P. Menon

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 70-74

Technical Paper / dx.doi.org/10.13182/NSE61-A25932

Examination of the Range of Applicability of Conditional Monte Carlo to Deep Penetration Problems

S. K. Penny, C. D. Zerby

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 75-82

Technical Paper / dx.doi.org/10.13182/NSE61-A25933

The Fast Effect in Uranium and Beryllium Systems

Herbert Rief

Nuclear Science and Engineering / Volume 10 / Number 1 / May 1961 / Pages 83-89

Technical Paper / dx.doi.org/10.13182/NSE61-A25934

Number 2

Table of Contents
Critical Heat Flux for Water in Swirling Flow(R. Viskanta)
Radioisotope Techniques(Vincent P. Guinn)

An Application of the Reciprocity Theorem to the Acceleration of Monte Carlo Calculations

C. W. Maynard

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 97-101

Technical Paper / dx.doi.org/10.13182/NSE61-A25945

The Single-Scattering Approximation to the Solution of the Gamma-Ray Air-Scattering Problem

D. K. Trubey

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 102-116

Technical Paper / dx.doi.org/10.13182/NSE61-A25946

Slowing Down from an Energy Distributed Neutron Source

A. Keane

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 117-119

Technical Paper / dx.doi.org/10.13182/NSE61-A25947

The Effect of Temperature on Xenon Instability

J. Chernick, G. Lellouche, W. Wollman

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 120-131

Technical Paper / dx.doi.org/10.13182/NSE10-2-120

Spherical Harmonic Calculations for a Cylindrical Cell of Finite Height

N. Tralli, J. Agresta

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 132-141

Technical Paper / dx.doi.org/10.13182/NSE61-A25949

Inelastic Scattering of Neutrons by U²³⁸ below 1 Mev

Lawrence Dresner

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 142-150

Technical Paper / dx.doi.org/10.13182/NSE61-A25950

Investigation on the Inelastic Moderation of Fast Neutrons

C. A. Heusch, T. Springer

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 151-158

Technical Paper / dx.doi.org/10.13182/NSE61-A25951

Minimum Critical Mass in Variable Density and Epithermal Reactors

Mathew M. Shapiro

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 159-162

Technical Paper / dx.doi.org/10.13182/NSE61-A25952

The Solubility of Nickel in Sodium by a Tracer Technique

T. A. Kovacina, R. R. Miller

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 163-166

Technical Paper / dx.doi.org/10.13182/NSE61-A25953

Doppler Broadening of Low-Energy Neutron Resonances

A. W. Solbrig, Jr.

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 167-168

Technical Paper / dx.doi.org/10.13182/NSE61-A25954

Low-Energy Neutron Resonances in Eu¹⁵¹

S. Tassan, A. Hellsten, V. L. Sailor

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 169-172

Technical Paper / dx.doi.org/10.13182/NSE61-A25955

Thermionic Reactor Systems

R. C. Howard

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 173-182

Technical Paper / dx.doi.org/10.13182/NSE61-A25956

Application of Rapid Fission Gas Analyses to an Off-Gas System Test

R. C. Koch, G. L. Grandy, J. A. Roll

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 183-189

Technical Paper / dx.doi.org/10.13182/NSE61-A25957

A Variational Procedure for Determining Spatially Dependent Thermal Spectra

G. P. Calame, F. D. Federighi

Nuclear Science and Engineering / Volume 10 / Number 2 / June 1961 / Pages 190-201

Technical Paper / dx.doi.org/10.13182/NSE61-A25958

Number 3

Table of Contents
Comparative Effects of Radiation(Titus C. Evans)
Abstract No. 14(M. A. Friedman, P. F. Zweifel)
Abstract No. 15(C. Eicheldinger)

Few Group Calculations of Thermal Neutron Transport

M. Goldsmith, R. M. Cantwell

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 207-218

Technical Paper / dx.doi.org/10.13182/NSE61-A25962

Exact Solution of the Slowing-Down Equation

Roman Bednarz

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 219-222

Technical Paper / dx.doi.org/10.13182/NSE61-A25963

Temperature Distributions of Reactor Fuel Element End Caps

K. R. Merckx

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 223-227

Technical Paper / dx.doi.org/10.13182/NSE61-A25964

Donald G. Gardner

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 228-234

Technical Paper / dx.doi.org/10.13182/NSE61-A25965

U²³⁸ Radiative Capture in PWR-2 Blanket Geometry

W. Baer

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 235-239

Technical Paper / dx.doi.org/10.13182/NSE61-A25966

Two-Group Theory of a Ring of N Cylindrical Rods or Zones in a Reflected Reactor

M. S. Trasi

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 240-246

Technical Paper / dx.doi.org/10.13182/NSE61-A25967

Correlation and Predicfion of Explosive Metal-Water Reaction Temperatures

Leo F. Epstein

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 247-253

Technical Paper / dx.doi.org/10.13182/NSE61-A25968

Applications of Geometric Theory to Nonlinear Reactor Dynamics

Elias P. Gyftopoulos

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 254-268

Technical Paper / dx.doi.org/10.13182/NSE61-A25969

Hydrodynamic Models for the Treatment of Reactor Thermal Transients

J. E. Meyer

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 269-277

Technical Paper / dx.doi.org/10.13182/NSE61-A25970

The Connection of Zircaloy-2 with Stainless Steel for Operation over a Wide Temperature Range

C. Gordon Duff

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 278-284

Technical Paper / dx.doi.org/10.13182/NSE61-A25971

Diffusion Lengths in Heterogeneous Media

Joel H. Ferziger, George S. C. Wang, P. F. Zweifel

Nuclear Science and Engineering / Volume 10 / Number 3 / July 1961 / Pages 285-294

Technical Paper / dx.doi.org/10.13182/NSE61-A25972

Number 4

Table of Contents
Spatial Dependence of Thermal-Neutron Spectra and the Interpretation of Thermal Utilization Measurements(Robert W. Deutsch)
Measurements of Relative Pu Fission Rates in Slightly Enriched Uranium—Water Lattices(J. J. Volpe, D. Klein)
Proposed Reactor Radiation Damage Monitor(S. I. Taimuty)
Nuclear Energy in Industry(Titus G. LeClair)
Radiation Hazards and Protection(Lauriston S. Taylor)
Resonance Absorption in Nuclear Reactors(Norman C. Francis)
Nuclear Data Tables, Part 3; Nuclear Reaction Graphs(Alan B. Smith)

Particle Self-Shielding in Plates Loaded with Spherical Poison Particles

W. B. Doub

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 299-307

dx.doi.org/10.13182/NSE61-A15371

Cross Sections of Threshold Reactions for Fission Neutrons: Nickel as a Fast Flux Monitor

T. O. Passell, R. L. Heath

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 308-315

dx.doi.org/10.13182/NSE61-A15372

Formation and Control of Turbidity in Aluminum-Water Reactor Systems

S. R. Hatcher, H. K. Rae

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 316-330

dx.doi.org/10.13182/NSE61-A15373

Nuclear Reactors with Maximum Prompt Neutron Lifetime

J. Ernest Wilkins, Jr.

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 331-336

dx.doi.org/10.13182/NSE61-A15374

Mean Square Instability in Boiling Reactors

A. Z. Akcasu

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 337-345

dx.doi.org/10.13182/NSE61-A15375

A Radiochemical Technique for the Determination of Short-Lived Fission Gases

Charles W. Townley, James E. Howes, Jr., Gilbert E. Raines, Ward S. Diethorn, Duane N. Sttnderman

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 346-351

dx.doi.org/10.13182/NSE61-A15376

Asymptotic Reactor Theory

K. M. Case, Joel H. Ferziger, P. F. Zweifel

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 352-356

dx.doi.org/10.13182/NSE61-A15377

Consistent P₁ Criticality Calculations

P. F. Zweifel, Joel H. Ferziger

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 357-361

dx.doi.org/10.13182/NSE61-A15378

Escape-Probabilities in Asymptotic Reactor Theory

S. Yip, P. F. Zweifel

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 362-366

dx.doi.org/10.13182/NSE61-A15379

Laboratory Development of the Acid Thorex Process For Recovery of Thorium Reactor Fuel

R. H. Rainey, J. G. Moore

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 367-371

dx.doi.org/10.13182/NSE61-A15380

On the Range of Validity of Nonlinear Reactor Dynamics

Elias P. Gyftopoulos, Jacques Devooght

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 372-376

dx.doi.org/10.13182/NSE61-A15381

Comparison of Wilkins Equation with Experiments on Water Systems

Luis de Sobrino, Melville Clark, Jr.

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 377-383

dx.doi.org/10.13182/NSE61-A15382

Comparison of the Wilkins Equation and Higher Order Approximations for Solid Moderators

Luis de Sobrino, Melville Clark, Jr.

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 384-387

dx.doi.org/10.13182/NSE61-A15383

A Study of Wilkins Equation

Luis de Sobrino, Melville Clark, Jr.

Nuclear Science and Engineering / Volume 10 / Number 4 / August 1961 / Pages 388-399

dx.doi.org/10.13182/NSE61-A15384