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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE62-A26103