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Number 1

Table of Contents
Radiation Damage in Crystals (D. R. de Halas)
Theory of Groups in Classical and Quantum Physics, Vol. I: Mathematical Structures and the Foundations of Quantum Theory (H. C. Schweinler)
On the Continuous Eigenvalue Spectrum of the Neutron-Wave Experiment (1) (J. J. Duderstadt)
On the Continuous Eigenvalue Spectrum of the Neutron-Wave Experiment (2) (M. N. Moore)
Reactor Kinetics Analysis by an Inverse Method (R. L. Murray, C. R. Bingham, C. F. Martin)

Integral Measurements of the Epithermal Neutron Capture-to-Fission Cross-Section Ratios of ²³³U and ²³⁵U
D. E. Conway and S. B. Gunst
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 1-6
Technical Paper | doi.org/10.13182/NSE67-A17804
Threshold Detector Cross-Section Intercalibration in a Pure Fission Spectrum
A. M. Bresesti, M. Bresesti, and R. A. Rydin
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 7-14
Technical Paper | doi.org/10.13182/NSE67-A17805
Thermal-Neutron Spectrum Measurements By Foil Activation
H. Ibarra, Jr. and R. Sher
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 15-27
Technical Paper | doi.org/10.13182/NSE67-A17806
Scattering and Self-Shielding Corrections in Cadmium-Filtered Gold, Indium, and 1/v Foil-Activation Measurements
S. Pearlstein and E. V. Weinstock
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 28-42
Technical Paper | doi.org/10.13182/NSE67-A17807
Invariant Imbedding and Polyenergetic Neutron Transport Theory—Part I: Theory
Andre Mockel
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 43-50
Technical Paper | doi.org/10.13182/NSE67-A17808
Invariant Imbedding and Polyenergetic Neutron Transport Theory—Part II: Numerical Results
Andre Mockel
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 51-57
Technical Paper | doi.org/10.13182/NSE67-A17809
The Use of Noether's Theorem in Reactor Physics
M. A. Tavel, B. E. Clancy, and G. C. Pomraningt
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 58-66
Technical Paper | doi.org/10.13182/NSE67-A17810
Statistical Analysis of Estimates for the Power Spectral Density in Neutron Multiplying Systems
E.J. McGrath and Robert W. Albrecht
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 67-86
Technical Paper | doi.org/10.13182/NSE67-A17811
Physics of Periodically Pulsed Reactors and Boosters: Steady-State Conditions, Power Pulse Characteristics, and Kinetics
J. A. Larrimore
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 87-110
Technical Paper | doi.org/10.13182/NSE67-A17812
The Effective Resonance Integral and Doppler Coefficient of Thorium-Oxide Rods
J. Hardy, Jr. and B. L. Palowitch
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 111-121
Technical Paper | doi.org/10.13182/NSE67-A17813
Diffusion of Xenon in Uranium Monocarbide
H. Shaked, D. R. Olander, and T. H. Pigford
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 122-130
Technical Paper | doi.org/10.13182/NSE67-A17814
Choked-Flow Analogy for Very Low Quality Two-Phase Flows
Frederick G. Hammitt, M. John Robinson, and J. F. Lafferty
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 131-142
Technical Paper | doi.org/10.13182/NSE67-A17815
Aggradation of Fluorocarbons from CF₄ and Carbon in Nuclear Reactor Radiation
William C. Askew and T. M. Reed III
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 143-144
Technical Paper | doi.org/10.13182/NSE67-A17816
Burnup Determination in an L54 Water-Boiler Reactor from Buildup of Tritium in its Recombiner Water
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 145-147
Technical Note | doi.org/10.13182/NSE67-A17817
Neutron-Capture Cross Section of 35-h ¹⁰⁵Rh
L. E. Glendenin and Henry C. Griffin
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 147-148
Technical Note | doi.org/10.13182/NSE67-A17818
Extrapolation Distance for Anisotropic Scattering
Lambros Lois and Herbert Goldstein
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 148-149
Technical Note | doi.org/10.13182/NSE67-A17819
Transient Spectra in Beryllium
A. K. Ghatak
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 149-151
Technical Note | doi.org/10.13182/NSE67-A17820
Density Transformations for Time-Dependent Radiation Transport Problems
Clayton D. Zerby
Nuclear Science and Engineering | Volume 29 | Number 1 | July 1967 | Pages 151-153
Technical Note | doi.org/10.13182/NSE67-A17821

Number 2

Table of Contents
Internal Conversion Processes (Guy T. Emery)
Irradiation Damage to Solids (D. K. Holmes)
Introduction to Nuclear Physics (David L. He trick)
Beryllium, Its Metallurgy and Properties (Frank Kerze, Jr.)
EXTERMINATOR-2 (T. B. Fowler, M. L. Tobias, D. R. Vondy)
WIGL2 (A. V. Vota)

Vaporization of Fission Products from Irradiated Fuels—I. Experimental Method and General Fission-Product Behavior
A. W. Castleman, Jr., I. N. Tang
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 159-164
Technical Paper | doi.org/10.13182/NSE67-A18523
Correlation of Radiation Damage to Steel with Neutron Spectrum
W.F. Sheely
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 165-175
Technical Paper | doi.org/10.13182/NSE67-A18524
Buffering of Uranium Monocarbide to Control Carbon Activity
W. Chubb
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 176-179
Technical Paper | doi.org/10.13182/NSE67-A18525
An Intrinsic Method for Determining Absolute Thermal Flux and Power in Heterogeneous Reactors
G. E. Goring
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 180-188
Technical Paper | doi.org/10.13182/NSE67-A18526
Secondary-Dose Equivalent Model and Comparison of 160-MeV Proton-Induced Neutron and Proton Dose with a Comprehensive Experiment
Bobby Liley, Arthur G. Duneer, Jr.
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 189-197
Technical Paper | doi.org/10.13182/NSE67-A18527
Spatial Dependence of Slowing Down Times for 14.1-MeV Neutrons in Water
Shee-Ming Chen, Leon J. Lidofsky
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 198-209
Technical Paper | doi.org/10.13182/NSE67-A18528
Charged Particle Slowing Down Spectra and Energy-Loss Distribution Resulting from Fast-Neutron Irradiation of Water
Richard E. Faw
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 210-217
Technical Paper | doi.org/10.13182/NSE67-A18529
Capture Cross Sections of Neptunium-237
Donald C. Stupegia, Marcia Schmidt, Curtis R. Keedy
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 218-219
Technical Paper | doi.org/10.13182/NSE67-A18530
A Derivation of Variational Principles for Inhomogeneous Equations
G. C. Pomraning
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 220-236
Technical Paper | doi.org/10.13182/NSE67-A18531
Singular Difference Approximations for the Discrete Ordinate Equations in x-y Geometry
J. A. Davis, L. A. Hageman, R. B. Kellogg
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 237-243
Technical Paper | doi.org/10.13182/NSE67-A18532
Concerning Infinitely Dilute Resonance Integrals
Coleridge A. Wilkins, Donald G. Thompson
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 244-247
Technical Paper | doi.org/10.13182/NSE67-A18533
One-Speed Neutron Transport in Slab Geometry
S. Pahor
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 248-253
Technical Paper | doi.org/10.13182/NSE67-A18534
Spectrum and Importance Function in Spatially Independent Fast-Reactor Assemblies
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 254-263
Technical Paper | doi.org/10.13182/NSE67-A18535
State Variable Feedback Control of Multiregion Reactors
Lynn E. Weaver, Robert E. Vanasse
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 264-271
Technical Paper | doi.org/10.13182/NSE67-A18536
A Procedure for Evaluating Modified Pulsed-Neutron- Source Experiments in Subcritical Nuclear Reactors
Christopher F. Masters, K. B. Cady
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 272-282
Technical Paper | doi.org/10.13182/NSE67-3
Interpretation of Pulsed-Source Experiments in the Peach Bottom HTGR
C. A. Preskitt, E. A. Nephew, J. R. Brown, K. R. Van Howe
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 283-295
Technical Paper | doi.org/10.13182/NSE67-4
Buckling Measurements in Water-Moderated and -Reflected Exponential Experiments
Henry H. Windsor
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 296-298
Technical Note | doi.org/10.13182/NSE67-A18539
The Mismatch of Thermal and Epithermal Neutron Flux
K. B. Cady, G. J. Kirouac, J. J. McInerney
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 299-302
Technical Note | doi.org/10.13182/NSE67-A18540
Solutions of the Time-Dependent One-Group Diffusion Equations for Reflected Systems
Rudolph Sher
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 302-305
Technical Note | doi.org/10.13182/NSE67-A18541
The Extrapolated Endpoint for the Milne Problem
G. C. Pomraning, K. D. Lathrop
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 305-308
Technical Note | doi.org/10.13182/NSE67-A18542
Subcritical Reactivity from Neutron Statistics
Arthur J. Lindeman, Lawrence Ruby
Nuclear Science and Engineering | Volume 29 | Number 2 | August 1967 | Pages 308-310
Technical Note | doi.org/10.13182/NSE67-A18543

Number 3

Table of Contents
Annual Review of Nuclear Science, Volume 16, 1966 (G. A. Bartholomew, C. Broude, M. Harvey, W. B. Lewis)
Reply To Comment on a Paper Discussing Hot-Channel Factors (F. D. Judge)
Comment on a Paper Discussing Hot-Channel Factors (Henri M. Guéron)

A Consistent Heterogeneous Theory of Reflected Lattices
T. Auerbach
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 317-324
Technical Paper | doi.org/10.13182/NSE67-A17279
The Dancoff Correction in Square and Hexagonal Lattices
I. Carlvik
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 325-336
Technical Paper | doi.org/10.13182/NSE67-A17280
The Method of Solution-Functions: A Computer-Oriented Solution of Boundary Value Problems as Applied to Nuclear Reactors—Part 1. Cylindrical Reactors in ρ-θ Geometry
Renato Bobone
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 337-353
Technical Paper | doi.org/10.13182/NSE67-A17281
Analysis of Pulsed-Neutron Experiments in Moderators via a Simple Model
Noel Corngold, Kanat Durgun
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 354-366
Technical Paper | doi.org/10.13182/NSE67-A17282
Measurement of the Prompt Neutron Decay Constant of the NORA Reactor by the Interval Distribution Technique
Dušan Babala and Rudolf Ogrin
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 367-372
Technical Paper | doi.org/10.13182/NSE67-A17283
Prompt-Neutron Kinetics of a Spherical-Cavity Reactor
Walter N. Podney, Harold P. Smith, Jr.
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 373-380
Technical Paper | doi.org/10.13182/NSE67-A17284
The Solution of the Space-Time Neutron Group Diffusion Equations by a Time-Discontinuous Synthesis Method
J. B. Yasinsky
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 381-391
Technical Paper | doi.org/10.13182/NSE67-A17285
Solution of the Reactor Kinetics Equations by Analytic Continuation
John C. Vigil
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 392-401
Technical Paper | doi.org/10.13182/NSE29-03-392
Methods for Collapsing Fast-Reactor Neutron Cross Sections
W. W. Little, Jr., R. W. Hardie
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 402-407
Technical Paper | doi.org/10.13182/NSE67-A17287
Measurements of the Protactinium-233 Resonance Integral
J. C. Connor, R. T. Bayard, D. Macdonald, S. B. Gunst
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 408-414
Technical Paper | doi.org/10.13182/NSE67-A17288
Total Neutron Cross Section of ²³²U
O. D. Simpson, M. S. Moore, J. R. Berreth
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 415-422
Technical Paper | doi.org/10.13182/NSE67-A17289
Total Neutron Cross Section of ²²⁸Th for the 1.9- and 7.5-eV Resonances
O. D. Simpson, R. P. Schuman, J. R. Berreth
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 423-424
Technical Paper | doi.org/10.13182/NSE67-A17290
Comparative Measurements of Uranium Atom Emission from Fissioning Surfaces
P. J. Peterson and M. M. Thorpe
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 425-431
Technical Paper | doi.org/10.13182/NSE67-A17291
Gamma-Ray Spectra of the Products of Fast-Neutron Fission of ²³⁵U and ²³⁸U at Selected Times After Fission
L. R. Bunney, D. Sam
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 432-443
Technical Paper | doi.org/10.13182/NSE67-A17292
Neutron Fluxes in Concrete Ducts Arising from Incident Thermal Neutrons: Calculation and Experiment
R. E. Maerker, F. J. Muckenthaler
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 444-454
Technical Paper | doi.org/10.13182/NSE67-A17293
A Solution of the Corngold Equation: Resulting Thermal-Neutron Spectra and Constants
Ernest Park Sims, Charles J. Bridgman
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 455-458
Technical Note | doi.org/10.13182/NSE67-A17294
Boundary Perturbations in Multigroup Diffusion Theory
N. Spinks
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 458-462
Technical Note | doi.org/10.13182/NSE67-A17295
The Effective Resonance Integral of 30-mil Thorium Wire Relative to the Integral at Infinite Dilution
A. B. Rothman, J. C. Connor, D. E. Conway
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 462-464
Technical Note | doi.org/10.13182/NSE67-A17296