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Volume 32

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Number 1

Table of Contents
STRIP(J. Helholtz, D. H. Roy)
RAUMZEIT(C. H. Adams, W. M. Stacey, Jr)
M0899(L. L. Lynn)
Molten Salts Handbook(Richard H. Wiswall, Jr.)
Electrons, Ions, and Waves(Igor Alexeff)
Experiments in Modern Physics(Hermann J. Donnert)
Nuclear Physics(Richard K. Osborn)
Unitary Symmetries and Their Application to High Energy Physics(F. F. Cap)
Comments on Two Papers on the Nonlinear Diffusion Equation(José Canosa)
Concerning Comments on Two Papers on the Nonlinear Diffusion Equation(Robert E. Lynch)
Comments on Canosa's Letter Regarding the Nonlinear Diffusion Equation(Richard Scalettar)

A Two-Dimensional Turbulent-Flow Mixing Model for Parallel-Flow Rod Bundles

Phillip A. Lowe

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE68-A18817

In-Pile Heat-Transfer Studies of Roughened Helium-Cooled Reactor Fuel Elements

C. A. Brandon, G. J. Kidd, Jr.

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 8-15

Technical Paper / dx.doi.org/10.13182/NSE68-A18818

The Influence of Axial Conduction on the Thermal Entry-Region Heat Transfer in Magnetohydrodynamic Channel Flow

Chia-Jung Hsu, George C. Lindauer

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 16-29

Technical Paper / dx.doi.org/10.13182/NSE68-A18819

Fission-Spectrum-Averaged Cross-Section Measurement for the ⁹Be (n, 2n) Reaction

L. Green

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 30-34

Technical Paper / dx.doi.org/10.13182/NSE68-A18820

Selected Fission Cross Sections for ²³²Th, ²³³U, ²³⁴U, ²³⁵U, ²³⁶U, ²³⁷Np, ²³⁸U, ²³⁹Pu, ²⁴⁰Pu, ²⁴¹Pu, and ²⁴²Pu

William G. Davey

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 35-45

Technical Paper / dx.doi.org/10.13182/NSE68-A18821

Half-Lives of Radionuclides—III

S. A. Reynolds, J. F. Emery, E. I. Wyatt

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 46-48

Technical Paper / dx.doi.org/10.13182/NSE68-A18822

The Measurement of Short-Lived Delayed Photoneutrons from Fission-Fragment Gamma Rays of ²³⁵U in Heavy Water

R. J. Onega, P. W. Forbes, A. K. Furr, A. Robeson

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 49-55

Technical Paper / dx.doi.org/10.13182/NSE68-A18823

The Validity of the Straightahead Approximation in Space-Vehicle Shielding Studies—Part II

R. G. Alsmiller, Jr., D. C. Irving, H. S. Moran

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 56-61

Technical Paper / dx.doi.org/10.13182/NSE68-A18824

A Method for the Calculation of Neutron-Capture Gamma-Ray Spectra

K. J. Yost

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 62-75

Technical Paper / dx.doi.org/10.13182/NSE68-A18825

Mathematical Verification of a Certain Monte Carlo Sampling Technique and Applications of the Technique to Radiation Transport Problems

W. A. Coleman

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 76-81

Technical Paper / dx.doi.org/10.13182/NSE68-1

A New Synthesis Method for Pulsed-Neutron Experiments

J. Devooght, C. Machgeels

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 82-92

Technical Paper / dx.doi.org/10.13182/NSE68-A18827

Excitation of Higher Space Modes in Reactor Transfer Function Measurement (Part I)

Genn Saji

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 93-100

Technical Paper / dx.doi.org/10.13182/NSE68-A18828

Extensions of Asymptotic Neutron Diffusion Theory

Alan M. Winslow

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 101-110

Technical Paper / dx.doi.org/10.13182/NSE68-A18829

An Exact Solution of Milne's Problem with a General Scattering Law

T. Trombetti

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 111-119

Technical Paper / dx.doi.org/10.13182/NSE68-A18830

Biorthogonal Angular Polynomial Expansion of the Two-Dimensional Transport Equation

K. D. Lathrop, N. S. Demuth

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 120-130

Technical Paper / dx.doi.org/10.13182/NSE68-A18831

Average Cross Sections and Resonance Integrals of ^242mAm

S. T. Perkins, G. F. Auchampaugh, R. W. Hoff, C. D. Bowman

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 131-132

Technical Note / dx.doi.org/10.13182/NSE68-A18832

Half-Life of ⁵⁴Mn

W. H. Zimmer, R. E. Dahl

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 132-133

Technical Note / dx.doi.org/10.13182/NSE68-A18833

Minimum Thickness of a Water-Reflected Infinite Slab of an Aqueous Solution of ²³⁵UO₂F₂ at Optimum Concentration

J. Wallace Webster

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 133-135

Technical Note / dx.doi.org/10.13182/NSE68-A18834

Minimum Critical ²³⁵U Enrichment of Homogeneous, Hydrogenous Uranyl Nitrate Systems

S. R. Bierman, G. M. Hess

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 135-139

Technical Note / dx.doi.org/10.13182/NSE68-A18835

Energy Correlation in a Moderating Nonmultiplying Medium

W. J. Turner

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 139-140

Technical Note / dx.doi.org/10.13182/NSE68-A18836

One-Velocity Calculations for the Analysis of Reactor Physics Experiments

P. d'Oultremont, M. Van Malder

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 140-142

Technical Note / dx.doi.org/10.13182/NSE68-A18837

Reactor Noise Measurements Using Gamma Rays

Wayne K. Lehto, John M. Carpenter

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 142-146

Technical Note / dx.doi.org/10.13182/NSE68-A18838

An Optimal Control of a Distributed-Parameter Reactor

Sang Hyon Kyong

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 146-149

Technical Note / dx.doi.org/10.13182/NSE68-A18839

Number 2

Table of Contents
FIGRO(L. L. Lynn)
2DB: A Two-Dimensional Fast-Reactor Burnup Code(W. W. Little, Jr., R. W. Hardie)
GLUB-1(L. L. Lynn)
Completeness in Science(Robert T. Lagemann)
The New Age in Physics(Roger W. Clapp, Jr.)
Sourcebook on Atomic Energy(William C. Pettus)
Servomechanisms(M. A. Schultz)
Radiation Heat Transfer(C. L. Tien)
Doppler Effect in Fissioning Plasma Reactors(H. F. Atwater)
Comments on Massel and Feix's Technical Note on Neutron Diffusion Using a Modulated Source(M. J. Ohanian)

Characteristics of a Tapered Cascade for Isotope Separation by Gaseous Diffusion

Kunio Higashi, Akio Oya, Jun Oishi

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 159-165

Technical Paper / dx.doi.org/10.13182/NSE68-A19728

Gamma Radiation Fluxes Near a Ground-Air Interface Using an Image Source Technique

C. Eisenhauer

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 166-177

Technical Paper / dx.doi.org/10.13182/NSE68-A19729

A Formalism for Calculation of Neutron Induced Gamma-Ray Production Cross Sections and Spectra

R. J. Howerton, E. F. Plechaty

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 178-183

Technical Paper / dx.doi.org/10.13182/NSE68-A19730

Calculation of the Penetration of Gamma Rays Through Slabs by the Method of Invariant Imbedding

A. Shimizu

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 184-194

Technical Paper / dx.doi.org/10.13182/NSE68-A19731

Some Neutron Reaction Cross Sections for ^{111, 112}Cd, ⁸⁷Sr, and ⁵⁸Ni

J. K. Temperley

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 195-200

Technical Paper / dx.doi.org/10.13182/NSE68-A19732

Study of Lattices of Graphite with Empty Channels by Means of the Pulsed Source Technique

V. Deniz, J. G. Le Ho, M. Sagot

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 201-224

Technical Paper / dx.doi.org/10.13182/NSE68-A19733

A New Method of Approximation of the Boltzmann Equation

Pierre Benoist, Alain Kavenoky

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 225-232

Technical Paper / dx.doi.org/10.13182/NSE68-A19734

Interface Conditions for Few-Group Neutron Diffusion Equations with Flux-Adjoint Weighted Constants

A. J. Buslik

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 233-240

Technical Paper / dx.doi.org/10.13182/NSE68-A19735

Formal Solution to the Neutron Moderation Problem in Nonhydrogenous Infinite Homogeneous Media

Leib Finkelstein

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 241-248

Technical Paper / dx.doi.org/10.13182/NSE68-A19736

The Study of One-Speed Multiregion Transport Problems in Plane Geometry by the Method of Boundary Sources

R. Beauwens, J. Devooght

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 249-261

Technical Paper / dx.doi.org/10.13182/NSE68-A19737

On the Use of ¹⁶⁴Dy, ¹⁷⁶Lu, and ²³⁹Pu in Thermal-Neutron Spectrum Determinations

J. J. Volpe

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 262-264

Technical Note / dx.doi.org/10.13182/NSE68-A19738

Effective Cadmium Cutoff Energies for Finite Cylindrical Filters with Finite-Size Detectors

S. S. Glickstein, W. J. Hall

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 264-265

Technical Note / dx.doi.org/10.13182/NSE68-A19739

Resonance Parameters for ²³⁶U from Integral Measurements

N. P. Baumann, J. D. Halford, D. J. Pellarin

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 265-267

Technical Note / dx.doi.org/10.13182/NSE68-A19740

A Technique for the Determination of Ratios of Effective Cross Sections from Reactor Fuel Burnup Data

R. P. Matsen

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 267-270

Technical Note / dx.doi.org/10.13182/NSE68-A19741

The C_n Method of Approximating the Boltzmann Equation in Cylindrical Geometry

Pierre Benoist, Alain Kavenoky

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 270-271

Technical Note / dx.doi.org/10.13182/NSE68-A19742

Approximate Zero-Power Describing Function Valid at All Frequencies

A. Ziya Akcasu, Louis M. Shotkin

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 271-273

Technical Note / dx.doi.org/10.13182/NSE68-A19743

On Controllability of Neutron-Flux Distribution

Nobuhide Suda

Nuclear Science and Engineering / Volume 32 / Number 2 / May 1968 / Pages 273-274

Technical Note / dx.doi.org/10.13182/NSE68-A19744

Number 3

Table of Contents
The Synthesis Method of Uncertainty Analysis in Nuclear Reactor Thermal Design(Henri Fenech, Henri M. Gueron)
The Design and Analysis of Scientific Experiments(Margaret K. Butler)

Reactor Physics Parameters of 1.03% Enriched Uranium Metal, D₂O Moderated Lattices

Walter H. D'Ardenne, Henry E. Bliss, David D. Lanning, Irving Kaplan and Theos J. Thompson

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 283-291

Technical Paper / dx.doi.org/10.13182/NSE68-A20210

Prompt Neutron Decay and Reactivity Measurements in Subcritical Uranium Metal Cylinders

J. T. Mihalczo

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 292-301

Technical Paper / dx.doi.org/10.13182/NSE68-A20211

Anisotropic Neutron Slowing Down in Aluminum-Water Mixtures-I: Experiments

Philip F. Palmedo

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 302-312

Technical Paper / dx.doi.org/10.13182/NSE68-A20212

Anisotropic Neutron Slowing Down in Aluminum-Water Mixtures-II: Monte Carlo Calculations

Philip F. Palmedo

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 313-318

Technical Paper / dx.doi.org/10.13182/NSE68-A20213

Monte Carlo Criticality Calculations for Thermal Reactors

M. R. Mendelson

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 319-331

Technical Paper / dx.doi.org/10.13182/NSE68-A20214

The Asymmetric Source Method of Measuring Reactor Shutdown

J. F. Walter and A. F. Henry

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 332-341

Technical Paper / dx.doi.org/10.13182/NSE68-A20215

Asymptotic Solutions to the Transport Equation for a Plane Lattice

A. Leonard

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 342-349

Technical Paper / dx.doi.org/10.13182/NSE68-A20216

The Thermal-Neutron Milne Problem and the Albedo of a Semi-Infinite Absorbing Medium-I: Theory

André Mockel

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 350-356

Technical Paper / dx.doi.org/10.13182/NSE68-A20217

Ray Effects in Discrete Ordinates Equations

K. D. Lathrop

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 357-369

Technical Paper / dx.doi.org/10.13182/NSE68-4

Reflection and Refraction of Neutron Diffusion Waves

R. Kladnik

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 370-376

Technical Paper / dx.doi.org/10.13182/NSE68-A20219

Parametric Fit of the Total Neutron Cross Section of Manganese from 0.01 eV to 50 keV

Thomas E. Stephenson and Sol Pearlstein

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 377-384

Technical Paper / dx.doi.org/10.13182/NSE68-A20220

Calculation of the Penetration of Gamma Rays Through Two-Layer Slabs

A. Shimizu

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 385-391

Technical Paper / dx.doi.org/10.13182/NSE68-A20221

Gamma Rays from Bombardment of Light and Intermediate Weight Nuclei by 16- to 160-MeV Protons and 59-MeV Alpha Particles

W. Zobel, F. C. Maienschein, J. H. Todd, and G. T. Chapman

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 392-406

Technical Paper / dx.doi.org/10.13182/NSE68-A20222

Diffusion Model for Release of Fission Products from Coated Particle Fuels

R. W. Dunlap and T. D. Gulden

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 407-416

Technical Paper / dx.doi.org/10.13182/NSE68-A20223

Interrelation of Nuclear Reactor Kinetic Experiments

J. L. Russell, Jr., W. Rotter

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 417-420

Technical Note / dx.doi.org/10.13182/NSE68-A20224

Nuclear Resonance Spacings and Synthetic Kernels

C. A. Wilkins, C. Chiarella, A. J. Gilks, A. Reichel

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 420-422

Technical Note / dx.doi.org/10.13182/NSE68-A20225

Exact Treatment of the Resonance Absorption of Neutrons of Intermediate Energy

Yukio Ishiguro

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 422-425

Technical Note / dx.doi.org/10.13182/NSE68-A20226

On the Application of Time-Synthesis Techniques to Coupled Core Reactors

J. B. Yasinsky

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 425-429

Technical Note / dx.doi.org/10.13182/NSE68-A20227

Statistical Analysis of Static Power Tilting in Reactors Due to Manufacturing Tolerances

F. D. Judge

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 429-430

Technical Note / dx.doi.org/10.13182/NSE68-A20228

The Effect of Fission Density on Fission-Gas Release

R. M. Carroll, O. Sisman, and R. B. Perez

Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 430-431

Technical Note / dx.doi.org/10.13182/NSE68-A20229