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Volume 29

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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)
Comment on a Paper Discussing Hot-Channel Factors(Henri M. Guéron)
Reply To Comment on a Paper Discussing Hot-Channel Factors(F. D. Judge)

A Consistent Heterogeneous Theory of Reflected Lattices

T. Auerbach

Nuclear Science and Engineering / Volume 29 / Number 3 / September 1967 / Pages 317-324

Technical Paper / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE67-A17296