Home / Publications / Journals / Nuclear Science and Engineering / Volume 23

Volume 23

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Number 1

Table of Contents
Rare Earth Research, II(Don M. Yost)
Atomic Migration in Crystals(O. C. Simpson)
Reactor Shielding(R. L. Ashley)
Comment on the Effect of Resonance Correction to Group Flux in Fast-Reactor Doppler-Effect Calculation(R. B. Nicholson)

Phase Equilibria in the Plutonium-Cerium-Copper System

L. J. Wittenberg, D. E. Etter, J. E. Selle, P. A. Tucker

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE65-A19253

Energy Distributions of Fission Fragments from Uranium Dioxide Films

Steve Kahn, Randall Harman, Vernon Forgue

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 8-20

Technical Paper / dx.doi.org/10.13182/NSE65-A19254

Radiometric Sensing of Atomic Hydrogen in Trace Quantities

Richard L. Bersin

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 21-27

Technical Paper / dx.doi.org/10.13182/NSE65-A19255

A Last-Collision Approach to Calculating the Angular Distribution of Fast Neutrons Penetrating a Shield

R. L. French

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 28-33

Technical Paper / dx.doi.org/10.13182/NSE65-A19256

Neutron-Spectrum Measurements in H₂O and D₂O

J. C. Young, J. M. Neill, D. H. Houston, J. R. Beyster

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 34-44

Technical Paper / dx.doi.org/10.13182/NSE65-A19257

Measurement of the U²³⁵ Neutron Capture-to-Fission Ratio, α, for Incident Neutron Energies from 3.25 eV to 1.8 keV

G. deSaussure, L. W. Weston, R. Gwin, J. E. Russell and R. W. Hockenbury

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 45-57

Technical Paper / dx.doi.org/10.13182/NSE65-A19258

Criticality Calculations for Uniform Water-Moderated Lattices

L. E. Strawbridge, R. F. Barry

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 58-73

Technical Paper / dx.doi.org/10.13182/NSE65-A19259

Pulsed-Decay and Extrapolation-Length Measurements in Graphite

S. K. Davis, J. A. De Juren, M. Reier

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 74-81

Technical Paper / dx.doi.org/10.13182/NSE65-A19260

Improvements to the Theory of Resonance Escape in Heterogeneous Fuel: II. The Dancoff Factor and the Equivalence Theorem in Cluster-Type Fuel

D. C. Leslie, A. Jonsson

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 82-89

Technical Paper / dx.doi.org/10.13182/NSE65-A19261

On the Theory of Space-Dependent Neutron Spectra in Heterogeneous Reactors II

Helmut Kunze

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 90-97

Technical Paper / dx.doi.org/10.13182/NSE65-A19262

Effect of Resonance Correction to Group Flux in Fast-Reactor Doppler-Effect Calculation

H. H. Hummel, R. N. Hwang

Nuclear Science and Engineering / Volume 23 / Number 1 / September 1965 / Pages 98-99

Technical Note / dx.doi.org/10.13182/NSE65-A19263

Number 2

Table of Contents
The Solvent Extraction of Metal Chelates(J. C. White)
Radioisotopic Power Generation(Richard Madey)
Numerical Methods of Reactor Analysis(Paul Michael)
Effect of Bragg Cutoff on the Diffusion of Thermal Neutrons in Graphite(Feroz Ahmed)
CCA - 112(R. A. Blaine)
CCA - 113(G. R. Dalton)
CCA - 114(Charles W. Friend, J. R. Knight)

Mass-Fission-Yield Curve for Americium-241

R. R. Rickard, C. F. Goeking, E. I. Wyatt

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 115-118

Technical Paper / dx.doi.org/10.13182/NSE65-A28135

Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part I

C. K. Sanathanan, J. C. Carter, F. Miraldi

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 119-129

Technical Paper / dx.doi.org/10.13182/NSE65-A28136

Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part II

C. K. Sanathanan, J. C. Carter, F. Miraldi

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 130-137

Technical Paper / dx.doi.org/10.13182/NSE65-A28137

Differential Dose-Rate Measurements of Backscattered Gamma Rays from Concrete, Aluminum and Steel

L. G. Haggmark, T. H. Jones, N. E. Scofield, W. J. Gurney

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 138-149

Technical Paper / dx.doi.org/10.13182/NSE65-A28138

Criticality of Homogeneous Plutonium Oxide-Plastic Compacts at H:Pu=15

C. R. Richey, J. D. White, E. D. Clayton, R. C. Lloyd

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 150-158

Technical Paper / dx.doi.org/10.13182/NSE65-A28139

The Decay of Equilibrium Neutron Flux Inside Beryllium Blocks at Different Temperatures

I. C. Goyal, L. S. Kothari

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 159-166

Technical Paper / dx.doi.org/10.13182/NSE65-A28140

Equilibrium Spectra and Diffusion Lengths of Neutrons in Semi-Infinite Moderator Block: Part II: Effect of ‘Trapped’ and Cold Neutrons

P. S. Grover, L. S. Kothari

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 167-169

Technical Paper / dx.doi.org/10.13182/NSE65-A28141

New Approximate Solution of Space- and Energy-Dependent Reactor Kinetics

Tsutomu Hoshino, Jiro Wakabayashi, Shigenori Hayashi

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 170-182

Technical Paper / dx.doi.org/10.13182/NSE65-A28142

A Simplified Nonlinear Model for Qualitative Study of Reactor Power-Distribution Transients

H. Hurwitz, Jr.

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 183-187

Technical Paper / dx.doi.org/10.13182/NSE65-A28143

Nuclear-Fuel-Depletion Measuring Device

L. B. Freeman

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 188-189

Technical Note / dx.doi.org/10.13182/NSE65-A28144

Fission-Product Effects in Molten Chloride Fast-Reactor Fuels

M. G. Chasanov

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 189-190

Technical Note / dx.doi.org/10.13182/NSE65-A28145

Neutron Diffusion Theory

J. D. Stewart

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 190-192

Technical Note / dx.doi.org/10.13182/NSE65-A28146

The Energy-Dependent Total Neutron Cross Section of Polyethylene

S. B. Armstrong

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 192-194

Technical Note / dx.doi.org/10.13182/NSE65-A28147

Inelastic Scattering of Slow Neutrons by Zirconium and Titanium Hydrides

S. S. Pan, F. J. Webb

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 194-197

Technical Note / dx.doi.org/10.13182/NSE65-A28148

Some Remarks on the Reduction of Thermal-Neutron Activation Rates to a Differential Spectrum

H. Ibarra, R. Sher

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 197-199

Technical Note / dx.doi.org/10.13182/NSE65-A28149

Number 3

Table of Contents
Nuclear Reactor Kinetics(Joseph A. Thie)
Complementary Use of Pulsed-Neutron and Reactor-Noise Measurements(S. R. Bierman, K. L. Garlid,R. W. Albrecht)

Fission-Gas Release from Pyrolytic-Carbon-Coated Fuel Particles During Irradiation at 2000 to 2500°F

P. E. Reagan, J. G. Morgan and O. Sisman

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 215-223

Technical Paper / dx.doi.org/10.13182/NSE65-A19554

Measured and Predicted Thermal- and Fast-Neutron Fluxes in Air-Filled Annular Ducts

J. Nilsson and R. Sandlin

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 224-233

Technical Paper / dx.doi.org/10.13182/NSE65-A19555

An Analogy Between the Variational Principles of Reactor Theory and those of Classical Mechanics

S. Kaplan

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 234-237

Technical Paper / dx.doi.org/10.13182/NSE65-A19556

Analysis of (n, 2n) Cross Sections for Medium and Heavy Mass Nuclei

S. Pearlstein

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 238-250

Technical Paper / dx.doi.org/10.13182/NSE65-A19557

Diffusion Length for Arbitrarily Anisotropic Scattering

E. Inönü and A. I. Usseli

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 251-255

Technical Paper / dx.doi.org/10.13182/NSE65-A19558

The Age of Fission Neutrons to Indium Resonance Energy in Zirconium-Water Mixtures Part I—Experiment

R. K. Paschall

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 256-263

Technical Paper / dx.doi.org/10.13182/NSE65-A19559

Age of Fission Neutrons to Indium Resonance Energy in Water and Zirconium-Water Mixtures (Part II—Theory)

Harry Alter

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 264-271

Technical Paper / dx.doi.org/10.13182/NSE65-A19560

The Calculation of Collision Probabilities in Cluster-Type Fuel Elements

D. C. Leslie, A. Jonsson

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 272-290

Technical Paper / dx.doi.org/10.13182/NSE23-03-272

The Asymptotic Angular-Dependent Leakage Spectrum of Thermal Neutrons

R. Kladnik

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 291-298

Technical Paper / dx.doi.org/10.13182/NSE65-A19562

Energy Loss by Fission Fragments in Nitrogen

Robert C. Axtmann and John T. Sears

Nuclear Science and Engineering / Volume 23 / Number 3 / November 1965 / Pages 299-305

Technical Paper / dx.doi.org/10.13182/NSE65-A19563

Number 4

Table of Contents
Controlled Thermonuclear Reactions(Albert Simon)
Decay Constant of a Neutron Pulse Inside a Finite Solid Moderator Assembly(L. S. Kothari)
Decay Constant of a Neutron Pulse(Noel Corngold)
On the Use of the Poincaré-Bertrand Formula in Neutron Transport Theory(I. Kuščer, N. J. McCormick)
A Note on the Adjoint Function in the Time Optimal Xenon Shutdown Problem(Jeffery Lewins)

Evaluation of Thermocouple Thermal-Loading Errors for a Surface-Attached Thermocouple on a Flat-Plate Fuel Element

J. H. Brindley

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 313-328

Technical Paper / dx.doi.org/10.13182/NSE65-A21067

Axial Heat Conduction in Reactor Fuel Elements

J. F. Thorpe

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 329-334

Technical Paper / dx.doi.org/10.13182/NSE65-A21068

The Solubility of Helium in Uranium Dioxide

Firooz Rufeh, Donald R. Olander and Thomas H. Pigford

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 335-338

Technical Paper / dx.doi.org/10.13182/NSE65-A21069

An Attempt to Measure Directly the Slowing Down Age of (D,D) Neutrons in Paraffin

B. Grimeland and G. Seierstad

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 339-343

Technical Paper / dx.doi.org/10.13182/NSE65-A21070

Calculation of Differential Fast-Neutron Spectra from Threshold-Foil Activation Data by Least-Squares Series Expansion Methods

G. Di Cola and A. Rota

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 344-353

Technical Paper / dx.doi.org/10.13182/NSE65-A21071

Thermal-Neutron-Induced-Recoil Defects in Cadmium Sulfide

Robert B. Oswald, Jr., and Chihiro Kikuchi

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 354-360

Technical Paper / dx.doi.org/10.13182/NSE65-A21072

Study of a Slightly Enriched UO₂ Lattice with H:U=0.42 — Measurement and Analysis

W. Baer, J. Hardy, Jr., D. Klein, J. J. Volpe, B. L. Palowitch and F. S. Frantz, Jr.

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 361-367

Technical Paper / dx.doi.org/10.13182/NSE65-A21073

Resonance Capture and Doppler Coefficient in Cylindrical Uranium Fuel Elements

T. D. Beynon, I. S. Grant

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 368-379

Technical Paper / dx.doi.org/10.13182/NSE65-A21074

Polarization Effects on Neutron Transport

George I. Bell and Walter B. Goad

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 380-391

Technical Paper / dx.doi.org/10.13182/NSE65-A21075

Doppler Coefficient Measurements for ²³⁵U in Fast-Reactor Spectra

P. I. Amundson, J. M. Gasidlo

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 392-393

Technical Note / dx.doi.org/10.13182/NSE65-A21076

Thermal Disadvantage Factors in Very Undermoderated Water-Uranium Oxide Lattices

Allen R. Boynton

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 393-395

Technical Note / dx.doi.org/10.13182/NSE65-A21077

A Method for Computing

G. C. Pomraning

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 395-397

Technical Note / dx.doi.org/10.13182/NSE65-A21078

Equivalence of the Time Optimal and Minimax Solutions to the Xenon Shutdown Problem

John J. Roberts, Harold P. Smith, Jr.

Nuclear Science and Engineering / Volume 23 / Number 4 / December 1965 / Pages 397-399

Technical Note / dx.doi.org/10.13182/NSE65-A21079