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Number 1
Number 2

Number 3
Number 4

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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)
Handbook of Chemistry and Physics (Melvin Tobias)
Management of Nuclear Materials (Ray C. Armstrong)

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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE61-A25915