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Volume 26

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Number 1

Determination of Radial Buckling in Reflected Systems

K. Serdula

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE66-A17182

Application of Langevin's Technique to Space-and Energy-Dependent Noise Analysis

A. Ziya Akcasu, R. K. Osborn

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 13-25

Technical Paper / dx.doi.org/10.13182/NSE66-A17183

Theoretical and Experimental Criteria for Nonlinear Reactor Stability

Elias P. Gyftopoulos

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 26-33

Technical Paper / dx.doi.org/10.13182/NSE66-A17184

Doppler Coefficient Measurements on Th and ThO2 Rods with Nonuniform Temperature Distributions

W. G. Pettus, and M. N. Baldwin

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 34-46

Technical Paper / dx.doi.org/10.13182/NSE66-A17185

The Neutron Spectrum in a UO2 Tube at Different Temperatures

E. Johansson, E. Jonsson, M. Lindberg, and J. Mednis

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 47-58

Technical Paper / dx.doi.org/10.13182/NSE66-A17186

Differential and Integral Thermal-Neutron Spectra in D20-Moderated Lattices

Sagid Salah and T. F. Parkinson

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 59-66

Technical Paper / dx.doi.org/10.13182/NSE66-A17187

The Effect of Randomness on Group Cross Sections, II

Charles N. Kelber and Philip H. Kier

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 67-72

Technical Paper / dx.doi.org/10.13182/NSE66-A17188

The Age of Fission Neutrons to Indium Resonance Energy in Aluminum-Water Mixtures

R. K. Paschall

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 73-79

Technical Paper / dx.doi.org/10.13182/NSE66-A17189

A Solution of Nonlinear Vibration Problems in Reactor Components

Amir N. Nahavandi and George J. Bohm

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 80-89

Technical Paper / dx.doi.org/10.13182/NSE66-A17190

Radiation-Damage Effects in Borated Graphite

J. M. Davidson, L. O. Gates, and R. E. Nightingale

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 90-98

Technical Paper / dx.doi.org/10.13182/NSE66-A17191

The Radiation Growth and Swelling Analysis for Cylind Fuel Elements During a Positive Reactor Period

Benjamin M. Ma

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 99-109

Technical Paper / dx.doi.org/10.13182/NSE66-A17192

Effect of Reactivity Addition Rate and of Weak Neutron Source on the Fission Yield of Uranium Solutions

Dale E. Hankins

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 110-116

Technical Paper / dx.doi.org/10.13182/NSE66-1

Skyshine Considerations for Accelerator Shielding Design

Carl H. Distenfeld and Robert D. Colvett

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 117-121

Technical Paper / dx.doi.org/10.13182/NSE66-A17194

Theoretical Investigations of Fission Product Deposition from Flowing Gas Streams

Ernest R. Venerus and M. Necati Ozisik

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 122-130

Technical Paper / dx.doi.org/10.13182/NSE66-A17195

Quantitative Evaluation of the Nordheim-Fuchs Reactor Excursion Model with Nonlinear Reactivity Feedback

A. Halim Kazi, James R. Tomonto, Bernard H. Cherry

Nuclear Science and Engineering / Volume 26 / Number 1 / September 1966 / Pages 131-133

Technical Note / dx.doi.org/10.13182/NSE66-A17196

Number 2

An Analysis of the Fission Cross Sections of 232Th, 233U, 234U, 235U, 236U, 237Np, 238U, 239Pu, 240Pu, 241PU, and 242Pu from 1 keV to 10 MeV

William G. Davey

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 149-169

Technical Paper / dx.doi.org/10.13182/NSE66-A28158

Energy-Dependent Neutron Transport Theory in Plane Geometry II. Eigenfunctions and Full-Range Completeness

A. Leonard, Joel H. Ferziger

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 170-180

Technical Paper / dx.doi.org/10.13182/NSE66-A28159

Energy-Dependent Neutron Transport Theory in Plane Geometry III. Half-Range Completeness and Half-Space Problems

A. Leonard, Joel H. Ferziger

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 181-191

Technical Paper / dx.doi.org/10.13182/NSE66-A28160

A New Approach to Half-Space Transport Problems

S. Pahor

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 192-197

Technical Paper / dx.doi.org/10.13182/NSE66-A28161

Calculating Space-Dependent Reactor Transfer Functions Using Statics Techniques

Charles E. Cohn, Robert J. Johnson and Robert N. Macdonald

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 198-206

Technical Paper / dx.doi.org/10.13182/NSE66-A28162

The Space Dependence of Reactor Noise—II Calculations

James R. Sheff, Robert W. Albrecht

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 207-221

Technical Paper / dx.doi.org/10.13182/NSE66-A28163

Improvements to the Theory of Resonance Escape in Heterogeneous Fuel III. Spatial Depression of the Resonance Flux

D. C. Leslie, J. G. Hill

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 222-229

Technical Paper / dx.doi.org/10.13182/NSE66-A28164

A Method of Calculating Resonance Absorption in a Circularized Cell

P. H. Kier

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 230-236

Technical Paper / dx.doi.org/10.13182/NSE66-A28165

Xenon-Induced Oscillations

José Canosa, Harvey Brooks

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 237-253

Technical Paper / dx.doi.org/10.13182/NSE66-A28166

Approximation for the Calculation of the Generalized First-Flight Collision Probability

Hiroshi Takahashi

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 254-261

Technical Paper / dx.doi.org/10.13182/NSE66-A28167

Time and Space Eigenvalues of the Boltzmann Equation with a Synthetic Thermalization Kernel

M. M. R. Williams

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 262-270

Technical Paper / dx.doi.org/10.13182/NSE66-A28168

Thermal Spectrum Measurements in Slightly Enriched Uranium, Light-Water-Moderated Lattices, by the Lutetium Activation Method

S. Tassan

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 271-276

Technical Paper / dx.doi.org/10.13182/NSE66-A28169

Transient Phenomenon in Diffusion Theory

A. K. Ghatak, L. S. Kothari

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 277-278

Technical Note / dx.doi.org/10.13182/NSE66-A28170

Use of Hexaiodobenzene as a Threshold Foil for Fast Neutrons

P. S. Spangler, N. C. Rasmussen, D. J. Rose

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 278-279

Technical Note / dx.doi.org/10.13182/NSE66-A28171

On the Disappearance of Discrete Decay Constants in Slabs

A. Mockel

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 279-281

Technical Note / dx.doi.org/10.13182/NSE66-A28172

Thermal Cross Section and Resonance Integrals of Cadmium-114

S. Pearlstein, R. F. Milligan

Nuclear Science and Engineering / Volume 26 / Number 2 / October 1966 / Pages 281-282

Technical Note / dx.doi.org/10.13182/NSE66-A28173

Number 3

The Flow of Boiling Water in Heated Pipes

Louis M. Shotkin

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 293-304

Technical Paper / dx.doi.org/10.13182/NSE66-A17350

Laminar Heat Transfer in a Hexagonal Channel with Internal Heat Generation and Unequally Heated Sides

Chi-Jung Hsu

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 305-318

Technical Paper / dx.doi.org/10.13182/NSE66-A17351

Maximum Temperatures in a Flat-Plate Fuel Element with Fuel-Clad Bonding Defects

D. S. Rowe, D. E. McFeron

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 319-328

Technical Paper / dx.doi.org/10.13182/NSE66-A17352

Irradiation Damage to Sintered Beryllium Oxide as a Function of Fast-Neutron Dose and Flux at 110, 650, and 1100°C

G. W. Keilholtz, J. E. Lee, Jr., R. E. Moore

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 329-338

Technical Paper / dx.doi.org/10.13182/NSE66-A17353

Measurements and Single-Velocity Calculations of Differential Angular Thermal-Neutron Albedos for Concrete

R. E. Maerker, F. J. Muckenthaler

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 339-346

Technical Paper / dx.doi.org/10.13182/NSE66-A17354

On the Velocity Distribution of Electrons Scattered from a Slab by the Gamma Flux from a Nuclear Explosion

C. D. Taylor

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 347-353

Technical Paper / dx.doi.org/10.13182/NSE66-A17355

The Dispersion Law of a Moderator

M. N. Moore

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 354-361

Technical Paper / dx.doi.org/10.13182/NSE66-A17356

The Reaction Rate of Neutrons in a Maxwellian Medium

Raymond L. Murray

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 362-365

Technical Paper / dx.doi.org/10.13182/NSE66-A17357

Comparison of Statistical Estimators for Neutron Monte Carlo Calculations

D. B. MacMillan

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 366-372

Technical Paper / dx.doi.org/10.13182/NSE66-A17358

Numerical Studies of Multichannel Variational Synthesis

E. L. Wachspress

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 373-377

Technical Paper / dx.doi.org/10.13182/NSE66-A17359

Stability Analysis of a Sampled-Data Controlled Nuclear Reactor System

Frigyes Reisch

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 378-384

Technical Paper / dx.doi.org/10.13182/NSE66-A17360

Perturbations, Mass, and Critical Mass

J. Devooght

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 385-392

Technical Paper / dx.doi.org/10.13182/NSE66-A17361

The Temperature Dependence to 1550°C of the Effective Resonance Integral of Thorium Oxide Rods

F. C. Schoenig, K. S. Quisenberry, D. P. Stricos, and H. Bernatowicz

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 393-398

Technical Paper / dx.doi.org/10.13182/NSE66-A17362

An Investigation of Resonance Absorption in Mixtures of Uranium-238 and Thorium-232

W. K. Foell, T. J. Connolly

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 399-417

Technical Paper / dx.doi.org/10.13182/NSE66-A17363

On the Theory of Rossi-Alpha Experiment in Reactor Noise Studies

Dušan Babala

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 418-419

Technical Note / dx.doi.org/10.13182/NSE66-A17364

Coupled-Reactors Kinetics Equations

H. Plaza, W. H. Köhler

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 419-422

Technical Note / dx.doi.org/10.13182/NSE66-A17365

Numerical Comparison of Methods of Describing Heavy-Element Neutron Slowing Down

L. B. Freeman, E. M. Gelbard

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Pages 422-424

Technical Note / dx.doi.org/10.13182/NSE66-A17366

Analytical Continuation and Laplace Transformation

Alois Schett

Nuclear Science and Engineering / Volume 26 / Number 3 / November 1966 / Page 424

Technical Note / dx.doi.org/10.13182/NSE66-A17367

Number 4

An Experimental Study of the Time Dependence of the Beta Energy Spectrum from 235U Fission Fragments

J. W. Kutcher, M. E. Wyman

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 435-446

Technical Paper / dx.doi.org/10.13182/NSE66-A18414

Asymptotic and Transient Spectra in Incoherent Media

S. K. Trikha, P. S. Grover

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 447-452

Technical Paper / dx.doi.org/10.13182/NSE66-A18415

Thermal-Neutron Flux Perturbation by Dysprosium-Aluminum Foils in Water and Uranyl Fluoride-Water Solutions

Donald F. Shook, Donald Bogart, Donald L. Alger-and Robert A. Muller

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 453-461

Technical Paper / dx.doi.org/10.13182/NSE66-A18416

Spatial Variation of the Fast Neutron Flux in Cells of Slightly 235U-Enriched-Uranium Water-Moderated Lattices

J. Hardy, Jr., D. Klein, and R. Dannels

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 462-471

Technical Paper / dx.doi.org/10.13182/NSE66-A18417

Time-Dependent Neutron Flux in Pulsed Multiplying Assemblies

F. D. Judge and P. B. Daitch

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 472-486

Technical Paper / dx.doi.org/10.13182/NSE66-A18418

The Neutron Capture Cross Section of the Tungsten Isotopes from 0.01 to 10 Electron Volts

S. J. Friesenhahn, E. Haddad, F. H. Fröhner, and W. M. Lopez

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 487-499

Technical Paper / dx.doi.org/10.13182/NSE66-A18419

Fast Neutron Scattering from Beryllium, Sodium, and Aluminum

J. P. Chien and A. B. Smith

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 500-510

Technical Paper / dx.doi.org/10.13182/NSE66-A18420

Detector Effects on the Statistics of Neutron Fluctuations

R. K. Osborn and J. M. Nieto

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 511-516

Technical Paper / dx.doi.org/10.13182/NSE66-A18421

Analytical Continuation for Calculating Multigroup-Multizone Eigenvalue Problems using Lie Series

Ferdinand Cap and Alois Schett

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 517-521

Technical Paper / dx.doi.org/10.13182/NSE66-A18422

Reciprocity in Time-Dependent Neutron Transport Theory

I. Kuščer and N. J. McCormick

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 522-529

Technical Paper / dx.doi.org/10.13182/NSE66-A18423

Iterative Solution of the Neutron Slowing Down Equation

M. W. Dyos and A. Keane

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 530-533

Technical Paper / dx.doi.org/10.13182/NSE66-A18424

Particle Transport and Heat Transfer in Gas-Solid Suspension Flow Under the Influence of an Electric Field

Kun Min and B. T. Chao

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 534-546

Technical Paper / dx.doi.org/10.13182/NSE66-A18425

Reactor Organic Coolants: I. Characteristics of Irradiated Hydrogenated Terphenyls

M. Tomlinson, J. L. Smee, E. B. Winters, and M. C. Arneson

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 547-558

Technical Paper / dx.doi.org/10.13182/NSE66-A18426

Explicit Forms for Scattering Transformation Matrices

D. R. Harris

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 559-562

Technical Note / dx.doi.org/10.13182/NSE66-A18427

Quasistatic Treatment of Spatial Phenomena in Reactor Dynamics

Karl Ott

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 563-565

Technical Note / dx.doi.org/10.13182/NSE66-A18428

Appendix to the Preceeding

John T. Madell

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 564-565

Technical Note / dx.doi.org/10.13182/NSE66-A18429

The Polya Model and the Distribution of Neutrons in a Steady-State Reactor

Nicola Pacilio

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 565-569

Technical Note / dx.doi.org/10.13182/NSE66-A18430

Reality of Relaxation Lengths in Various Approximate Forms of the Slab Transport Equation

E. M. Gelbard and S. Kaplan

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 569-571

Technical Note / dx.doi.org/10.13182/NSE66-A18431

Fast-Neutron Spectra in Water and Graphite

L. Harris, Jr., G. Sherwood, and J. S. King

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 571-573

Technical Note / dx.doi.org/10.13182/NSE66-A18432

Measurements of Effective (Self-shielded) Neutron Cross Sections by a Fast Pulsed Method

E. Arai, H. Miessner, and K. H. Beckurts

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 573-575

Technical Note / dx.doi.org/10.13182/NSE66-A18433

Production of 185mW in a Nuclear Reactor

Henry H. Kramer and Werner H. Wahl

Nuclear Science and Engineering / Volume 26 / Number 4 / December 1966 / Pages 575-577

Technical Note / dx.doi.org/10.13182/NSE66-A18434