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Volume 12

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Number 1

Table of Contents

Sorption of Xenon in High Density Graphite at High Temperatures

Frank J. Salzano, Allen M. Eshaya

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 1-3

Technical Paper / dx.doi.org/10.13182/NSE62-A25361

Adsorption of Xenon and Argon on Graphite

M. C. Cannon, W. R. Grimes, W. T. Ward, G. M. Watson

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 4-9

Technical Paper / dx.doi.org/10.13182/NSE62-A25362

A Variational Principle for Nonlinear Systems

Jeffery Lewins, Capt. RE

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 10-14

Technical Paper / dx.doi.org/10.13182/NSE62-A25363

Removal of the More Noble Nonvolatile Fission Products from Uranium-Bismuth Fuels

Orrington E. Dwyer, Herbert E. Howe, Edward R. Avrutik

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 15-22

Technical Paper / dx.doi.org/10.13182/NSE62-A25364

MTR-ETR Operating Experience

R. L. Doan

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 23-32

Technical Paper / dx.doi.org/10.13182/NSE62-A25365

Electrolytic Dissolution of Reactor Fuels

C. M. Slansky, M. W. Roberts, K. L. Rohde

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 33-38

Technical Paper / dx.doi.org/10.13182/NSE62-A25366

Oxidation and Heat Transfer Studies in Graphite Channels: I. The Effect of Air Flow Rate on the C-O₂ and CO-O₂ Reactions

Donald G. Schweitzer, George C. Hrabak, Robert M. Singer

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 39-45

Technical Paper / dx.doi.org/10.13182/NSE62-A25367

Oxidation and Heat Transfer Studies in Graphite Channels: II. Thermal Changes with Time and Distance in Air-Cooled Graphite Channels

Donald G. Schweitzer, David H. Gurinsky

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 46-50

Technical Paper / dx.doi.org/10.13182/NSE62-A25368

Oxidation and Heat Transfer Studies in Graphite Channels: III. The Chemical Reactivity of BNL Graphite and Its Effect on the Length of Channel Cooled by Air

Donald G. Schweitzer, Robert M. Singer

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 51-58

Technical Paper / dx.doi.org/10.13182/NSE62-A25369

Oxidation and Heat Transfer Studies in Graphite Channels: IV. Combined Effects of Temperature, Flow Rate, Diameter, and Chemical Reactivity on the Length of Channel Cooled by Air

Donald G. Schweitzer

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 59-62

Technical Paper / dx.doi.org/10.13182/NSE62-A25370

Neutron Resonance in Samarium

Brother Austin Bernabei, L. B. Borst, V. L. Sailor

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 63-67

Technical Paper / dx.doi.org/10.13182/NSE62-A25371

Interaction of Radiation and Matter, a Part of the Nuclear Engineering Curriculum

T. Kammash, H. J. Gomberg

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 68-70

Technical Paper / dx.doi.org/10.13182/NSE62-A25372

Solvent Extraction Experiments in Nuclear Fuels Processing

R. F. Makens, Dale E. Bush

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 71-78

Technical Paper / dx.doi.org/10.13182/NSE62-A25373

Laboratory Experiments Using a Pulsed Neutron Source

Russell B. Mesler, Harry G. O'Brien, Debow Freed

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 79-81

Technical Paper / dx.doi.org/10.13182/NSE62-A25374

An Electrical Analogy of Nuclear Reactor Neutron Flux

J. R. Eaton, R. L. Long

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 82-90

Technical Paper / dx.doi.org/10.13182/NSE62-A25375

Surface Film Formation in Heterogeneous and Homogeneous Reactors

W. E. Parkins

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 91-105

Technical Paper / dx.doi.org/10.13182/NSE62-A25376

Fission Product Trapping—Sorption of Cesium by Activated Charcoal

E. E. Anderson, G. L. Wessman, L. R. Zumwalt

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 106-110

Technical Paper / dx.doi.org/10.13182/NSE62-A25377

Remotely Operated Dispersion-Coalescence Tester

C. M. Slansky, O. W. Parrett, K. L. Rohde

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 111-114

Technical Paper / dx.doi.org/10.13182/NSE62-A25378

Fission-Product Capture Cross Sections

J. D. Garrison, B. W. Roos

Nuclear Science and Engineering / Volume 12 / Number 1 / January 1962 / Pages 115-134

Technical Paper / dx.doi.org/10.13182/NSE62-A25379

Number 2

Table of Contents
Transport Mean Free Path and Diffusion Length of Neutrons Calculated From Markov Chain Statistics(E. Richard Cohen)
Multiregion Fuel Elements(M. R. Fleishman, A. A. Strasser, J. E. Wilkins, Jr.)
Thermal Flux Disadvantage Factors for Slab Geometry(Chander P. Bhalla)
Slowing Down with Anisotropic Scattering(A. Keane, J. P. Pollard)
Introduction to Nuclear Engineering(Paul C. Zmola)
Protection Against Radiation(Karl Z. Morgan)
Reactor Heat Transfer(H. F. Poppendiek)
Numerical Methods for Nuclear Reactor Calculations(E. M. Gelbard)
Plasmas and Controlled Fusion(Norman Rostoker)
Reactors of the World—Second Series(Edward D. Jordan)
Introduction to Nuclear Engineering(Glen J. Schoessow)
Nuclear Reactors for Power Generation(V. E. Schrock)
Encyclopedic Dictionary of Electronics and Nuclear Engineering(S. H. Hanauer)
MIST(D. M. Shapiro)
GREEN(G. R. Dalton)
DETECTOR(G. R. Dalton)
TRAC-1(Jerome Spanier)

The Potential of Plutonium as a Fuel in Near-Thermal Converter Reactors

Karl H. Puechl

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 135-150

Technical Paper / dx.doi.org/10.13182/NSE62-A26051

The Potential of Plutonium as a Fuel in Near-Thermal Burner Reactors

KArl H. Puechl

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 151-156

Technical Paper / dx.doi.org/10.13182/NSE62-A26052

The Total Cross Section of Aluminium for Neutrons of Energies From 0.003 ev to 0.009 ev

D. Bally, S. Todireanu, S. Rîpeanu

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 157-159

Technical Paper / dx.doi.org/10.13182/NSE62-A26053

The Control System of the Ispra-1 Reactor

S. Barabaschi, A. Pulacci

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 160-168

Technical Paper / dx.doi.org/10.13182/NSE62-A26054

Neutron Capture to Fission Ratios in U²³³, U²³⁵, Pu²³³

J. C. Hopkins, B. C. Diven

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 169-177

Technical Paper / dx.doi.org/10.13182/NSE62-A26055

Backscattering of Gamma Rays

Tomonori Hyodo

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 178-184

Technical Paper / dx.doi.org/10.13182/NSE62-A26056

The Development of a Dilute Aluminum-Gold Alloy for Thermal and Resonance Neutron Flux Measurements

L. M. Howe, R. E. Jervis, T. A. Eastwood

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 185-189

Technical Paper / dx.doi.org/10.13182/NSE12-2-185

Measurement of Neutron Diffusion Parameters in Water by the Pulsed Neutron Method

W. M. Lopez, J. R. Beyster

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 190-202

Technical Paper / dx.doi.org/10.13182/NSE62-A26058

Thermoelastic Dynamics of Rods, Thin Shells, and Solid Spheres

David Burgreen

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 203-217

Technical Paper / dx.doi.org/10.13182/NSE62-A26059

Determination of Reactor Transfer Functions by Statistical Correlation Methods

V. Rajagopal

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 218-224

Technical Paper / dx.doi.org/10.13182/NSE62-A26060

The Performance of Metallic-Foil Insulations in Vertical Gas Spaces

R. E. MacPherson, Jr., H. D. Stuart

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 225-233

Technical Paper / dx.doi.org/10.13182/NSE62-A26061

Effectiveness of Lining Materials in Increasing the Blast Resistance of A Simulated Outer Containment Vessel for A Nuclear Reactor

J. W. Hanna, W. O. Ewing, Jr.

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 234-237

Technical Paper / dx.doi.org/10.13182/NSE62-A26062

Neutron Diffusion in a Temperature Gradient

J. R. L. de Ladonchamps, L. M. Grossman

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 238-242

Technical Paper / dx.doi.org/10.13182/NSE62-A26063

Total Neutron Cross Section of Pa²³¹

F. B. Simpson, W. H. Burgus, J. E. Evans, H. W. Kirby

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 243-249

Technical Paper / dx.doi.org/10.13182/NSE62-A26064

The Scattering of Thermal Neutrons by Moderators

P. A. Egelstaff

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 250-259

Technical Paper / dx.doi.org/10.13182/NSE62-A26065

On the Evaluation of the Thermal Neutron Scattering Law

P. A. Egelstaff, P. Schofield

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 260-270

Technical Paper / dx.doi.org/10.13182/NSE62-A26066

An Instrument for Nondestructively Testing Fuel Core to Cladding Heat Transfer

Donald R. Green

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 271-275

Technical Paper / dx.doi.org/10.13182/NSE62-A26067

A Three-Dimensional Depletion Analysis of the First Shippingport Pressurized Water Reactor

D. H. Jones, R. P. Christman

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 276-284

Technical Paper / dx.doi.org/10.13182/NSE62-A26068

Cesium Exchange Properties of Vermiculite

D. G. Jacobs

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 285-292

Technical Paper / dx.doi.org/10.13182/NSE62-A26069

Effective Resonance Integral of Thorium Metal

Alan B. Rothman, Charles E. W. Ward

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 293-300

Technical Paper / dx.doi.org/10.13182/NSE62-A26070

Measurement of the Dancoff Correction

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

Nuclear Science and Engineering / Volume 12 / Number 2 / February 1962 / Pages 301-308

Technical Paper / dx.doi.org/10.13182/NSE62-A26071

Number 3

Table of Contents
Spatial Dependence of Thermal-Neutron Spectra and the Interpretation of Thermal Utilization Measurements(R. Sher, H. Kouts)
Re: “Spatial Dependence of Thermal-Neutron Spectra and the Interpretation of Thermal Utilization Measurements”(Robert W. Deutsch)
A Note on the Measurement of Diffusion Parameters by the Pulsed-Neutron Source Technique(G. DeSaussure)
The Resonance Integral For Uranium Metal and Oxide(E. Hellstrand, G. Lundgren)
The Temperature Dependence of the Viscosity of Liquid Metals(Simon W. Strauss)
Measured Slowing Down Distribution at the Indium Resonance from a Line Source of Fission Neutrons in Heavy Water(W. E. Graves)
Radioisotope Applications Engineering(John P. Danforth)
Nuclear Radiation Measurement(W. W. Managan)
KARE(J. A. Archibald, Jr., E. D. Reilly, Jr.)
FLEER(J. L. Fletcher, J. P. Jewett, E. D. Reilly, Jr.)
TRAM(R. A. Pfeiffer, W. W. Stone)
Los Alamos Least Squares(Roger H. Moore)
9-RENUPAK (UNC-90-1)(J. Certaine, E. DeDufour, G. Rabinowitz)
9-NIOBE (UNC-90-2)(Stanley Preiser)

Kinetics of Structural Changes during Beta Transformation of Uranium

William R. McDonell

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 325-336

Technical Paper / dx.doi.org/10.13182/NSE62-A28082

Boron Trifluoride as a Soluble Poison in Molten Salt Reactor Fuels

J. H. Shaffer, W. R. Grimes, and G. M. Watson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 337-340

Technical Paper / dx.doi.org/10.13182/NSE62-A28083

Experimental Bucklings of Heavy Water Moderated Lattices of Natural Uranium Metal Rod Clusters

T. J. Hurley, Jr., H. R. Fike, and G. F. O'Neill

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 341-347

Technical Paper / dx.doi.org/10.13182/NSE62-A28084

Exponential Measurements of Natural Uranium Rods in Heavy Water and Comparisons with Critical Experiments

E. C. Wingfield and E. J. Hennelly

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 348-358

Technical Paper / dx.doi.org/10.13182/NSE62-A28085

Determination of Eta by Comparison of for U²³³ and Pu²³⁹ with for U²³⁵ in a Flux Trap Critical Assembly

R. Gwin, D. W. Magnuson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 359-363

Technical Paper / dx.doi.org/10.13182/NSE62-A28086

The Measurement of Eta and Other Nuclear Properties of U²³³ and U²³⁵ in Critical Aqueous Solutions

R. Gwin, D. W. Magnuson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 364-380

Technical Paper / dx.doi.org/10.13182/NSE62-A28087

Multichannel Flux Synthesis

E. L. Wachspress, R. D. Burgess, S. Baron

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 381-389

Technical Paper / dx.doi.org/10.13182/NSE62-A28088

An Analysis of Vapor Void Profiles in Heated Channels

Gerald Houghton

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 390-397

Technical Paper / dx.doi.org/10.13182/NSE62-A28089

Engineering Considerations for Remote Refabrication of EBR-II Fuel Elements

A. B. Shuck, J. E. Ayer

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 398-404

Technical Paper / dx.doi.org/10.13182/NSE62-A28090

Equipment for Remote Injection Casting of EBR-II Fuel

H. F. Jelinek, G. M. Iverson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 405-411

Technical Paper / dx.doi.org/10.13182/NSE62-A28091

Equipment for the Remote Demolding, Sizing, and Inspection of EBR-II Cast Fuel Pins

N. J. Carson, Jr., S. B. Brak

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 412-418

Technical Paper / dx.doi.org/10.13182/NSE62-A28092

Leak Testing of EBR-II Fuel Rods

A. P. Grunwald

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 419-423

Technical Paper / dx.doi.org/10.13182/NSE62-A28093

Assembling, Sodium Bonding, and Bond Testing of EBR-II Fuel Rods

T. C. Cameron, N. F. Hessler

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 424-431

Technical Paper / dx.doi.org/10.13182/NSE62-A28094

Number 4

Table of Contents
Group Averaging of Diffusion Coefficients(P. F. Zweifel, G. L. Ball)
Recursion Method for Calculating the Spatial Distribution of Resonance Absorptions(Harvey J. Amster)
Treatment of Annular Voids in Diffusion Theory(E. Garelis)
On the Influence of Pressure on Boiling Water Reactor Dynamic Behavior at Atmospheric Pressure(Richard L. Moore)
Radioactive Wastes. Their Treatment and Disposal(E. G. Struxness)
Controlled Thermonuclear Reactions. An Introduction to Theory and Experiment(Eugene Guth)
SAIL(B. J. Lemke)
SEAL-SHELL-1(Carl M . Friedrich)
TRG-RS(γ)(Herbert Steinberg)
TRG-RS(N)(Herbert Steinberg)
SHADOW(Herbert Steinberg)
TRIGR-S(Herbert Steinberg)
TRIGR-P(Herbert Steinberg)
ABCD(Herbert Steinberg)
Escape-Probabilities in Asymptotic Reactor Theory

The Void Coefficient in an Enriched, Water Reactor

Jerome L. Shapiro

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 449-456

Technical Paper / dx.doi.org/10.13182/NSE62-A26090

A New Calculation of Resonance Integrals

L. W. Nordheim

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 457-463

Technical Paper / dx.doi.org/10.13182/NSE62-A26091

The Slowing Down of Neutrons as a Stochastic Process

Zbigniew Weiss

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 464-468

Technical Paper / dx.doi.org/10.13182/NSE62-A26092

Criticality of Low Enrichment Uranium in Hydrogen

C. B. Mills, G. I. Bell

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 469-473

Technical Paper / dx.doi.org/10.13182/NSE62-A26093

Forced Convection Boiling in Tubes

V. E. Schrock, L. M. Grossman

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 474-481

Technical Paper / dx.doi.org/10.13182/NSE62-A26094

Space Dependent Xenon Oscillations

Gerald S. Lellouche

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 482-489

Technical Paper / dx.doi.org/10.13182/NSE62-A26095

The Effect on Calculated Clean Critical Activation Shapes of the Use of Transport Approximations in the Fast Groups

M. CANTWELL, M. GOLDSMITH

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 490-497

Technical Paper / dx.doi.org/10.13182/NSE62-A26096

Design of Radiation Chemical Reactors with Special Reference to the Polymerization of Ethylene

Melvin M. Levine, Meyer Steinberg

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 498-504

Technical Paper / dx.doi.org/10.13182/NSE62-A26097

A Measurement of the Effective Delayed Neutron Fraction for the Bulk Shielding Reactor-I

R. Perez-Belles, J. D. Kington, G. Desaussure

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 505-512

Technical Paper / dx.doi.org/10.13182/NSE62-A26098

The EQUIPOISE Method—A Simple Procedure for Group-Diffusion Calculations in Two and Three Dimensions

Melvin Tobias, T. B. Fowler

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 513-518

Technical Paper / dx.doi.org/10.13182/NSE62-A26099

Neutron Activation Cross Sections of Pm¹⁴⁷, Pm¹⁴⁸, and Pm^148m

R. P. Schuman, J. R. Berreth

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 519-522

Technical Paper / dx.doi.org/10.13182/NSE62-A26100

The Calculation of Effective Cutoff Energies in Cadmium, Samarium, and Gadolinium

G. D. Hickman, W. B. Leng

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 523-531

Technical Paper / dx.doi.org/10.13182/NSE62-A26101

Time Dependent, Space Independent Neutron Thermalization

Juan U. Koppel

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 532-541

Technical Paper / dx.doi.org/10.13182/NSE62-A26102

Albedo Logic for S_n Transport Analysis

Bernard H. Duane

Nuclear Science and Engineering / Volume 12 / Number 4 / April 1962 / Pages 542-544

Technical Paper / dx.doi.org/10.13182/NSE62-A26103