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Volume 27

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Number 1

Table of Contents
A Solution of the Space-Energy-Angle-Dependent Neutron Slowing-Down Problem(Joseph J. McInerney)
Application of Langevin's Technique to Space- and Energy-Department Noise Analysis(A. Ziya Akcazu, R. K. Osborn)
Exact Solution of The Problem of Goldstein and Cohen(T. S. Horner, A. Keane)
Nuclear Structure Study with Neutrons(G. D. James)
Nuclear Appplication of NonFissionable Ceramics(George W. Cunningham)
A Generalized Resonance Integral Correlation for Uranium Rods(L. E. Strawbridge)
A Plausibility Argument by B. Davison for the Completeness of the Elementary Solutions to the One-Dimensional Neutron-Transport Equation(W. L. Hendry)

Heat Transfer to Liquid Metals Flowing Turbulently in Eccentric Annuli—II

W. S. Yu, O. E. Dwyer

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE67-A18036

Material Bucklings for 1.002, 1.25, and 1.95 wt% Uranium-235-Enriched Uranium Tubes in Light Water

C. L. Brown, R. C. Lloyd

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 10-15

Technical Paper / dx.doi.org/10.13182/NSE67-A18037

Fast Neutron Spectroscopy by Proton-Recoil Proportional Counting

E. F. Bennett

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 16-27

Technical Paper / dx.doi.org/10.13182/NSE67-A18038

Neutron Spectrum Measurement in a Fast Critical Assembly

E. F. Bennett

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 28-33

Technical Paper / dx.doi.org/10.13182/NSE67-A18039

Direct Determination of Uranium-235 Capture-to-Fission Ratio in a Zero-Power Reactor

W. C. Redman, M. M. Bretscher

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 34-44

Technical Paper / dx.doi.org/10.13182/NSE67-A18040

Slowing Down of Neutrons in Zirconium Hydride

Pekka Jauho, Jussi Manninen

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 45-50

Technical Paper / dx.doi.org/10.13182/NSE67-A18041

Slowing Down Spectra of Neutrons in Lithium Hydride

V. V. Verbinski

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 51-66

Technical Paper / dx.doi.org/10.13182/NSE67-A18042

Angular Distributions of Low-Energy Neutrons Leaking from Various Scattering Materials

V. V. Verbinski

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 67-79

Technical Paper / dx.doi.org/10.13182/NSE67-A18043

Experimental Investigation of Fast Neutron Decays in Lead Assemblies

L. E. Beghain, F. Hofmann, S. Wilensky

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 80-84

Technical Paper / dx.doi.org/10.13182/NSE67-A18044

The Determination of the Fast-Fission Cross Section of Protactinium-233 with Fission Neutrons

H. R. von Gunten, R. F. Buchanan, A. Wyttenbach, K. Behringer

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 85-94

Technical Paper / dx.doi.org/10.13182/NSE67-A18045

Monte Carlo Calculations of Resonance Integral of ²³²Th

Bal Raj Sehgal

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 95-103

Technical Paper / dx.doi.org/10.13182/NSE67-A18046

Milne Problem for Thermal Neutrons with Absorption

Jacek Arkuszewski

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 104-119

Technical Paper / dx.doi.org/10.13182/NSE67-A18047

Stability Extrema in Nuclear Power Systems with Design Uncertainties

T. W. Kerlin

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 120-130

Technical Paper / dx.doi.org/10.13182/NSE67-A18048

Selective Ion-Exchange Sorption of Cesium-137 and Iodine-131 from Borated Solutions

B. N. Dickinson

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 131-132

Technical Note / dx.doi.org/10.13182/NSE67-A18049

An Improved Treatment of Scattering Resonances in Slab Geometry

Sanford C. Cohen

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 133-135

Technical Note / dx.doi.org/10.13182/NSE67-A18050

Influence of Molecular Binding Effects in Water on Measured Resonance Integrals

J. Hardy, Jr.

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 135-136

Technical Note / dx.doi.org/10.13182/NSE67-A18051

An Analytic Treatment of the “Flux Bump” in Resonance Absorption

G. C. Pomraning, M. W. Dyos

Nuclear Science and Engineering / Volume 27 / Number 1 / January 1967 / Pages 137-139

Technical Note / dx.doi.org/10.13182/NSE67-A18052

Number 2

Table of Contents

Calculations of the Radiation Hazard Due to Exposure of Supersonic Aircraft to Solar-Flare Protons

M. Leimdorfer, R. G. Alsmiller, Jr., and R. T. Boughner

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 151-157

Technical Paper / dx.doi.org/10.13182/NSE67-A18259

High-Energy Nucleon Transport and Space Vehicle Shielding

R. G. Alsmiller, Jr.

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 158-189

Technical Paper / dx.doi.org/10.13182/NSE67-A18260

Electron Transport Theory, Calculations, and Experiments

C. D. Zerby and F. L. Keller

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 190-218

Technical Paper / dx.doi.org/10.13182/NSE67-A18261

Adjoint and Importance in Monte Carlo Application

R. R. Coveyou, V. R. Cain, and K. J. Yost

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 219-234

Technical Paper / dx.doi.org/10.13182/NSE67-A18262

Variance of Certain Flux Estimators Used in Monte Carlo Calculations

Francis H. Clark

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 235-239

Technical Paper / dx.doi.org/10.13182/NSE67-1

A Study of the Angular and Energy Distributions of Radiation at Small Distances from a Point Source of Gamma Rays or Neutrons

Charles Eisenhauer

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 240-251

Technical Paper / dx.doi.org/10.13182/NSE67-A18264

Doses Behind Vertical and Horizontal Barriers from a Plane Source of 1.25 MeV Gamma-Ray Photon

Dominic J. Raso and Stanley Woolf

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 252-264

Technical Paper / dx.doi.org/10.13182/NSE67-A18265

Deep Penetration of Radiation by the Method of Invariant Imbedding

D. R. Mathews, K. F. Hansen, and E. A. Mason

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 263-270

Technical Paper / dx.doi.org/10.13182/NSE67-A18266

One-Velocity Neutron Transport Problems by the Transfer Matrix Method

Raphael Aronson

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 271-282

Technical Paper / dx.doi.org/10.13182/NSE67-A18267

Measurements and Calculations of the Spectral and Spatial Details of the Fast-Neutron Flux in Water Shields

V. V. Verbinski, M. S. Bokhari, J. C. Courtney, and G. E. Whitesidestt

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 283-298

Technical Paper / dx.doi.org/10.13182/NSE67-A18268

Measurements of the Spectra of Uncollided Fission Neutrons Transmitted Through Thick Samples of Nitrogen, Oxygen, Carbon, and Lead: Investigation of the Minima in Total Cross Sections

C. E. Clifford, E. A. Straker, F. J. Muckenthaler, V. V. Verbinski, R. M. Freestone, Jr., K. M. Henry, and W. R. Burrus

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 299-307

Technical Paper / dx.doi.org/10.13182/NSE67-A18269

Neutron-Attenuation Experiments in Iron-Water Configurations

B. Chinaglia and D. Monti, C. Fedrighini and A. M. Moncassoli

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 308-317

Technical Paper / dx.doi.org/10.13182/NSE67-A18270

Experimental Differential Number, Energy and Exposure Albedos for Sem-finite Media, for Normally Incident Gamma Photons

J. J. Steyn, D. G. Andrews

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 318-327

Technical Paper / dx.doi.org/10.13182/NSE67-A18271

Capture and Fission Gamma-Ray Effective Spectra for Shielding

Donald J. Dudziak

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 328-337

Technical Paper / dx.doi.org/10.13182/NSE67-A18272

High-Energy Accelerator Shield-Leakage Neutron Spectra

Keran O'Brien, Robert Sanna, Mary Alberg, James E. McLaughlin, and Sam A. Rothenberg

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 338-347

Technical Paper / dx.doi.org/10.13182/NSE67-A18273

Neutron Exposure of the PM-2A Reactor Vessel

K. Shure and Carl T. Oberg

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 348-359

Technical Paper / dx.doi.org/10.13182/NSE67-A18274

An Analysis of a Shielding Experiment Performed in a Real Fallout Field

R. L. French, J. H. Price, and K. W. Tompkins

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 360-366

Technical Paper / dx.doi.org/10.13182/NSE67-A18275

Neutron Air-Transport Data for the Design of Protective Structures

R. H. Karcher

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 367-387

Technical Paper / dx.doi.org/10.13182/NSE67-A18276

Investigation of the Floor-Barrier Reduction Factor Used In Structure Shielding Theory

A. L. Kaplan

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 388-393

Technical Paper / dx.doi.org/10.13182/NSE67-A18277

Gamma-Ray Scattering Near an Air-Ground Interface

E. T. Clarke

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 394-402

Technical Paper / dx.doi.org/10.13182/NSE67-A18278

The Close-in Exposure Field From Point Isotropic Gamma-Ray Source Located at an Air-Ground Interface

A. B. Chilton

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 403-410

Technical Paper / dx.doi.org/10.13182/NSE67-A18279

Calculation of Doubly Differential Current Albedos for Epicadmium Neutrons Incident on Concrete and Comparison of the Reflected Subcadmium Component with Experiment

W. A. Coleman, R. E. Maerker, F. J. Muckenthaler, and P. N. Stevens

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 411-422

Technical Paper / dx.doi.org/10.13182/NSE67-A18280

Monte Carlo Calculations, Using the Albedo Concept, of the Fast-Neutron Dose Rates along the Center Lines of One- and Two-Legged Square Concrete Open Ducts and Comparison with Experiment

R. E. Maerker and F. J. Muckenthaler

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 423-433

Technical Paper / dx.doi.org/10.13182/NSE67-A18281

On the Attenuation of Neutrons and Photons Duct Filled with a Helical Steel Plug

E. Aalto and Å. Krell

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 433-440

Technical Paper / dx.doi.org/10.13182/NSE67-A18282

Albedo Component of Gamma Rays Passing Through a Cylindrical Duct

Y. Higashihara, Masaru Nakai, Masanori Okubo,

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 441-449

Technical Paper / dx.doi.org/10.13182/NSE67-A18283

Gamma-Ray Streaming Through a Straight Cylindrical Duct

Mitsuo Shindo, Akira Tsuruo, Shun-ichi Miyasaka, Mitsuyuki Kitazume, Jun-ichi Miyakoshi

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 450-463

Technical Paper / dx.doi.org/10.13182/NSE67-A18284

Weight Optimization of Gamma-Ray Shields Using Layered Media and Spherical Geometry

Alfred F. Rohach

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 464-466

Technical Note / dx.doi.org/10.13182/NSE67-A18285

Empirical Formulas for Secondary-Nucleon-Production Cross Sections

W. R. Yucker

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Page 467

Technical Note / dx.doi.org/10.13182/NSE67-A18286

Few-Group and Multigroup Calculations of Neutron Penetration

K. Shure

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 468-471

Technical Note / dx.doi.org/10.13182/NSE67-A18287

Heating in Infinite Cylinders by Uniform Gamma-Ray Sources

C. W. Nestor, Jr., and H. C. Claiborne

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 472-474

Technical Note / dx.doi.org/10.13182/NSE67-A18288

A Markov Matrix Treatment of Neutron Diffusion in Thin Slabs

M. L. Eaton and C. M. Huddleston

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 475-477

Technical Note / dx.doi.org/10.13182/NSE67-A18289

Differential Neutron Albedo For Finite Slabs

Duane R. Doty

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 478-480

Technical Note / dx.doi.org/10.13182/NSE67-A18290

A Modified Formula for Differential Exposure Albedo for Gamma Rays Reflected from Concrete

A. B. Chilton

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 481-482

Technical Note / dx.doi.org/10.13182/NSE67-A18291

Air-Ground Interface Effects on the Exposure from Elevated ¹³⁷Cs y Sources

C. E. Clifford and G. D. Wait

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 483-484

Technical Note / dx.doi.org/10.13182/NSE67-A18292

The Small-Angle Limit for Twice-Scattered Gamma Rays from a Point-lsotropic Source

Edgar E. Morris and L. V. Spencer

Nuclear Science and Engineering / Volume 27 / Number 2 / February 1967 / Pages 485-487

Technical Note / dx.doi.org/10.13182/NSE67-A18293

Number 3

Table of Contents
Proceedings of the 1966 Heat Transfer and Fluid Mechanics Institute(Frederick G. Hammitt)
Neutron Dynamics and Control(M. A. Schultz)
Introductory Nuclear Theory (Second Edition)(J. Y. Park)
The Albedo Problem and Chadrasekhar H-Function II(I. K. Abu-Shumays)
Monte Carlo Calculations of Resonance Integral of 232Th(Bal Raj Sehgal)

Few-Group Approximations Based on a Variational Principle

A. F. Henry

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 493-510

Technical Paper / dx.doi.org/10.13182/NSE86-A17615

The Thermal-Neutron Milne Problem with a Two-Term Degenerate Kernel

M. M. R. Williams

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 511-519

Technical Paper / dx.doi.org/10.13182/NSE86-A17616

Scattering Functions for Low-Energy Neutron Collisions in a Maxwellian Monatomic Gas

G. Lansing Blackshaw, Raymond L. Murray

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 520-532

Technical Paper / dx.doi.org/10.13182/NSE86-A17617

Neutron-Flux Spectral Determination by Foil Activation

W. N. McElroy, S. Berg, G. Gigas

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 533-541

Technical Paper / dx.doi.org/10.13182/NSE86-A17618

Continuity Conditions for a Homogeneous or Heterogeneous P_N Approximation

James A. Davis

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 542-548

Technical Paper / dx.doi.org/10.13182/NSE86-A17619

Effects of the Flat-Flux and Infinite-Mass Approximation on Resonance Absorption

Hans Ludewig

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 549-556

Technical Paper / dx.doi.org/10.13182/NSE86-A17620

Multiplication Factor of Uranium Metal by One-Velocity Monte Carlo Calculations

John T. Mihalczo

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 557-563

Technical Paper / dx.doi.org/10.13182/NSE86-A17621

The Effect of Air Channels on the Diffusion Length of Thermal Neutrons in Light Water

Y. Segal, S. Zamir

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 564-567

Technical Paper / dx.doi.org/10.13182/NSE86-A17622

Fission-Neutron Age Measurements in Aluminum-Water Mixtures

J. D. Spencer, T. G. Williamson

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 568-572

Technical Paper / dx.doi.org/10.13182/NSE86-A17623

Experimental Application of the Time-Optimal Xenon Shutdown Program

John J. Roberts, R. F. Fleming, Harold P. Smith, Jr.

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 573-580

Technical Paper / dx.doi.org/10.13182/NSE86-A17624

The Influence of Source Geometry on Fission-Fragment Escape Properties

E. E. Lewis, R. Pfeffer

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 581-585

Technical Paper / dx.doi.org/10.13182/NSE86-A17625

Bremsstrahlung from ₉₀Sr-₉₀Y in Thin Absorbers

Thomas S. Bustard, Joseph Silverman

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 586-596

Technical Paper / dx.doi.org/10.13182/NSE86-A17626

A Method of Calculating Asymptotic and Transient Material Bucklings of a Uniform Rod Lattice

J. D. Stewart

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 597-598

Technical Note / dx.doi.org/10.13182/NSE86-A17627

The Boundary Conditions at the Interface between a Lattice Core and a Homogeneous Reflector

J. D. Stewart

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 598-600

Technical Note / dx.doi.org/10.13182/NSE86-A17628

Controllability of the Spatial Flux Shape

Donald M. Wiberg

Nuclear Science and Engineering / Volume 27 / Number 3 / March 1967 / Pages 600-604

Technical Note / dx.doi.org/10.13182/NSE86-A17629