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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)
Electrons, Ions, and Waves (Igor Alexeff)
Molten Salts Handbook (Richard H. Wiswall, Jr.)
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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)
The New Age in Physics (Roger W. Clapp, Jr.)
Completeness in Science (Robert T. Lagemann)
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE68-A20229