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Volume 9

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Number 1

Table of Contents
A One-Group Model for Thermal Activation Calculations(R. J. Breen)
Let the Reactor Prevent Xenon Instability(G. C. Fullmer)
Thermal Neutron Flux in a Cell with Temperature Discontinuities(D. S. Selengut)
Local Flux Distributions in ORR Fuel Elements(A. L. Colomb, J. F. Wett, Jr.)
Natural Abundances of Er¹⁷² and Yb¹⁶⁷(P. S. Baker, T. L. Collins)
Precision Measurements of the Slow Neutron Absorption Cross Sections of Normal Boron Standards(G. J. Safford, T. I. Taylor, B. M. Rustad, W. W. Havens, Jr.)

Control Rod Economics

W. K. Anderson C. J. Beck, J. S. Theilacker

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 1-15

Technical Paper / dx.doi.org/10.13182/NSE61-A25858

The Determination of Lattice Parameters by Means of Measurements on a Single Fuel Element

J. W. Zink, G. W. Rodeback

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 16-25

Technical Paper / dx.doi.org/10.13182/NSE61-A25859

Expansion Losses in Two-Phase Flow

P. A. Lottes

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 26-31

Technical Paper / dx.doi.org/10.13182/NSE61-A25860

Extraction of Plutonium from Uranium by Liquid Magnesium

M. W. Nathans, E. Greenberg, H. M. Feder

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 32-34

Technical Paper / dx.doi.org/10.13182/NSE61-A25861

Validity of the Homogenization Approximation for End-Leakage Calculations

Joe R. Beeler, Jr.

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 35-40

Technical Paper / dx.doi.org/10.13182/NSE61-A25862

Intensity of Unscattered Gamma Rays inside Cylindrical Self-Absorbing Sources

D. F. Rhodes, R. A. Stallwood, W. E. Mott

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 41-46

Technical Paper / dx.doi.org/10.13182/NSE61-A25863

SM-2 Flexible Critical Experiments

W. J. McCool, R. A. Robinson, E. W. Schrader, S. H. Weiss

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 47-54

Technical Paper / dx.doi.org/10.13182/NSE61-A25864

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. VI. The Behavior of Plutonium in the Melt-Refining Process

V. G. Tkice, Jr., N. R. Chellew

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 55-58

Technical Paper / dx.doi.org/10.13182/NSE61-A25865

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. VII. The Evolution of Xenon and Krypton

A. Schneider, N. R. Chellew

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 59-63

Technical Paper / dx.doi.org/10.13182/NSE61-A25866

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. VIII. The Behavior of Rare Earths, Yttrium, Barium, Strontium, and Cesium

N. R. Chellew, G. A. Bennett, V. G. Trice

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 64-70

Technical Paper / dx.doi.org/10.13182/NSE61-A25867

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. IX. Sorption and Retention of Sodium and Cesium Vapor on Stationary Beds at Elevated Temperature

J. Wolkoff, A. A. Chilenskas

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 71-77

Technical Paper / dx.doi.org/10.13182/NSE61-A25868

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. X. The Behavior of Zirconium

N. R. Chellew, V. G. Trice

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 78-81

Technical Paper / dx.doi.org/10.13182/NSE61-A25869

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. XI. Behavior of Iodine in Melt Refining

N. R. Chellew, M. Ader

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 82-86

Technical Paper / dx.doi.org/10.13182/NSE61-A25870

The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. XII. The Behavior of Ruthenium, Molybdenum, Palladium, Rhodium, Technetium, Antimony, Cadmium, and Tellurium

N. R. Chellew, G. A. Bennett

Nuclear Science and Engineering / Volume 9 / Number 1 / January 1961 / Pages 87-90

Technical Paper / dx.doi.org/10.13182/NSE61-A25871

Number 2

Table of Contents
The Density of Dilute Solutions of Copper in Liquid Lead(S. W. Strauss, L. E. Richards)
Reactivity Effect of (n, 2n) Reactions in D2O(H. K. Clark)
Formulas for Thermal Reactors with Some Resonance Fission(P. F. Gast)
Prediction of Thermal-Neutron Fluxes in the Bulk Shielding Facility from Lid Tank Shielding Facility Data(A. D. MacKellar)
Failure of Neutron Transport Approximations in Small Cells in Cylindrical Geometry(J. A. Thie)
Management of Nuclear Materials(Ray C. Armstrong)
Handbook of Chemistry and Physics(Melvin Tobias)

Eta of U²³³ from 1 to 800 ev

M. L. Yeater, R. W. Hockenbury, R. R. Fullwood

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 105-119

dx.doi.org/10.13182/NSE61-A15594

Cold Neutron Beams from Small Low-Temperature Moderators in Reactors

F. J. Webb

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 120-126

dx.doi.org/10.13182/NSE61-A15595

Error Propagation in Hot-Spot, Hot-Channel Analysis

Fred H. Tingey

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 127-131

dx.doi.org/10.13182/NSE61-A15596

Thermal Neutron Absorption Cross Sections by the Pulsed Source Method

J. W. Meadows, J. F. Whalen

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 132-136

dx.doi.org/10.13182/NSE61-A15597

Radiation Damage in Steel: Considerations Involving the Effect of Neutron Spectra

A. D. Rossin

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 137-147

dx.doi.org/10.13182/NSE61-A15598

Gamma Branching in Kr⁸⁵

W. S. Lyon

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 148-150

dx.doi.org/10.13182/NSE61-A15599

Comparison Theorems for the Estimation of Criticality in Bare, One-Velocity Reactors

Lawrence Dresner

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 151-156

dx.doi.org/10.13182/NSE61-A15600

Neutron Thermalization and Diffusion in Pulsed Media

S. N. Purohit

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 157-167

dx.doi.org/10.13182/NSE61-A15601

Measurements of Neutron Spectra in Water, Polyethylene, and Zirconium Hydride

J. R. Beyster, J. L. Wood, W. M. Lopez, R. B. Walton

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 168-184

dx.doi.org/10.13182/NSE61-A15602

On the Solution of Transport Problems by Conditional Monte Carlo

D. W. Drawbaugh

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 185-197

dx.doi.org/10.13182/NSE61-A15603

Flux Perturbations by Thermal Neutron Detectors

G. Ronald Dalton, Richard K. Osborn

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 198-210

dx.doi.org/10.13182/NSE61-A15604

Preparation and Characteristics of ThO₂-Bi Slurries

W. F. Kenney, H. Susskind

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 211-220

dx.doi.org/10.13182/NSE61-A15605

Age of Fission Energy Neutrons to Indium Resonance in Water

R. C. Doerner, R. J. Armani, W. E. Zagotta, F. H. Martens

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 221-240

dx.doi.org/10.13182/NSE61-A15606

An Approach to Reactor Physics Using Results of Integral Experiments

Karl H. Puechl

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 241-259

dx.doi.org/10.13182/NSE61-A15607

On the Maximization of the Sensitivity of a Fuel Assay Reactor

Henry A. Sandmeier

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 260-270

dx.doi.org/10.13182/NSE61-A15608

The Influence of Pressure on Boiling Water Reactor Dynamic Behavior at Atmospheric Pressure

Joseph A. Fleck, Jr.

Nuclear Science and Engineering / Volume 9 / Number 2 / February 1961 / Pages 271-280

dx.doi.org/10.13182/NSE61-A15609

Number 3

Table of Contents
Regarding “Elastic-Plastic Thermal Stresses in Tubes Subjected to Uniform Heat Generation Evaluation of Experimental Results Obtained Using Graphite Tubes”(D. R. Miller)
Rebuttal(T. Kammash)
Slowing-Down Time of Neutrons in Water(J. A. Dejuren)
Effect of Interference between Resonance and Potential Scattering on Resonance Absorption(George I. Bell)
FNR Shim-Safety Rod Deformations(C. W. Ricker, W. R. Dunbar)
Beta-Gamma Delayed Coincidence Method for Resonance Escape Measurements(Laurence S. Beller, Paul F. Zweifel)
Re: "An H₂O-D₂O Moderated Reactor"(John J. Happell)
Crack Formation in Uranium(K. R. Merckx)
Book Review(R. Ehrlich)
Book Review(H. M. Parker)

Reactivity Worth of the Central Fuel Element in the Bulk Shielding Reactor-I

G. Desaussure, K. Henry, R. Perez-Belles

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 291-298

Technical Paper / dx.doi.org/10.13182/NSE61-A25879

Niobium-20 w/o Uranium, High-Temperature Metallic Fuel of the Future

John A. De Mastry, Frederic R. Shober, Ronald F. Dickerson

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 299-304

Technical Paper / dx.doi.org/10.13182/NSE61-A25880

Time-Dependent Thermal-Neutron Energy Spectra in a Monatomic Heavy Gas

S. N. Purohit

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 305-313

Technical Paper / dx.doi.org/10.13182/NSE61-A25881

On the Design and Management of Fast Reactor Blankets

S. A. Hasnain, D. Okrent

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 314-322

Technical Paper / dx.doi.org/10.13182/NSE61-A25882

Formal Heat Transfer Solutions

C. F. Bonilla, J. S. Busch, H. G. Landau, L. L. Lynn

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 323-331

Technical Paper / dx.doi.org/10.13182/NSE61-A25883

Effect of Specific Power on Fuel Reactivity and Costs in Thorium-Fueled Reactors

E. A. Mason, J. A. Larrimore

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 332-340

Technical Paper / dx.doi.org/10.13182/NSE61-A25884

The Resonance Fission Integrals of U²³⁵, Pu²³⁹, and Pu²⁴¹

J. Hardy, Jr., D. Klein, G. G. Smith

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 341-345

Technical Paper / dx.doi.org/10.13182/NSE61-A25885

Circulating Fused-Salt Fuel Irradiation Test Loop

D. B. Trauger, J. A. Conlin, Jr.

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 346-356

Technical Paper / dx.doi.org/10.13182/NSE61-A25886

The Property of Finality and the Analysis of Problems in Reactor Space-Time Kinetics by Various Modal Expansions

S. Kaplan

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 357-361

Technical Paper / dx.doi.org/10.13182/NSE61-A25887

The Solution of the Reactor Kinetics Equations for Large and Small Excursions

J. C. Carter, Nye F. Morehouse, Jr.

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 362-366

Technical Paper / dx.doi.org/10.13182/NSE61-A25888

The Effect of Diffusion upon the Initial Phases of the Thermalization of Neutrons

Noel Corngold, Larry Zamick

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 367-369

Technical Paper / dx.doi.org/10.13182/NSE61-A25889

New Analytical Formula for Dancoff Correction for Cylindrical Fuel Lattices

Yuzo Fukai

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 370-376

Technical Paper / dx.doi.org/10.13182/NSE61-A25890

Minimum Critical Dimensions for Water Solutions

C. B. Mills

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 377-390

Technical Paper / dx.doi.org/10.13182/NSE61-A25891

A Comparison of Niobium-Vanadium and Niobium-Zirconium Alloys for Structural Applications in Boiling Water Reactors

D. L. Douglass

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 391-398

Technical Paper / dx.doi.org/10.13182/NSE61-A25892

The Reduction of the Time-Dependent Equations for Nuclear Reactors to a Set of Ordinary Differential Equations

Capt. J. Lewins

Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 399-407

Technical Paper / dx.doi.org/10.13182/NSE61-A25893

Number 4

Table of Contents
Measurement of Epithermal Neutron Spectra by Resonance Detectors(Hsiang-Lin Pai, Pu-Yuan Ma, Shin-Chen Wang, Wellington S. Lee)
Reactor Analysis(A. F. Henry)
Reactor Analysis, 2nd review(P. F. Zweifel)
Applied Gamma-Ray Spectrometry(W. H. Jordan)
Fast Neutron Physics Part I: Techniques(T. W. Bonner)

Diffusion of Lanthanides and Actinides from Graphite at High Temperatures

C. J. Orth

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 417-420

Technical Paper / dx.doi.org/10.13182/NSE61-A25905

Experimental Studies of U²³⁸ Resonance Neutron Capture in UO₂ Fuel Rods

G. G. Smith, J. Hardy, D. Klein, J. A. Mitchell

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 421-429

Technical Paper / dx.doi.org/10.13182/NSE61-A25906

The Effects of Atomic Motions on the Moderation of Neutrons

Donald E. Parks

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 430-441

Technical Paper / dx.doi.org/10.13182/NSE61-A25907

Transient Flow Performance in a Multiloop Nuclear Reactor System

George M. Boyd, Jr., Ralph M. Rosser, Bennett B. Cardwell, Jr.

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 442-454

Technical Paper / dx.doi.org/10.13182/NSE61-A25908

Purification of Irradiated Tributyl Phosphate by Distillation in Kerosene-Type Diluent

Fred Sicilio, T. H Goodgame, Bert Wilkins, Jr.

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 455-461

Technical Paper / dx.doi.org/10.13182/NSE61-A25909

High-Frequency Surface Thermal Fatigue Cycling of Inconel at 1405°F

J. J. Keyes, Jr., A. I. Krakoviak

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 462-474

Technical Paper / dx.doi.org/10.13182/NSE61-A25910

The Transuranium Elements

Glenn T. Seaborg

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 475-487

Technical Paper / dx.doi.org/10.13182/NSE61-A25911

New Developments in Uranium-Zirconium Alloy Fuel Reprocessing

T. A. Gens

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 488-494

Technical Paper / dx.doi.org/10.13182/NSE61-A25912

Equal Charge Displacement Rule in Fission Product Poisoning

Melvin M. Levine

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 495-499

Technical Paper / dx.doi.org/10.13182/NSE61-A25913

Solid State Electrolysis in Yttrium Metal

J. M. Williams, C. L. Huffine

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 500-506

Technical Paper / dx.doi.org/10.13182/NSE61-A25914

The Resonance Integral of Thorium Metal Rods

Eric Hellstrand, Jakob Weitman

Nuclear Science and Engineering / Volume 9 / Number 4 / April 1961 / Pages 507-518

Technical Paper / dx.doi.org/10.13182/NSE61-A25915