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Volume 34

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Number 1

Table of Contents
M0648(Lambros Lois)
LETO(Lambros Lois)
Scientific Progress and Human Values(Alvin M. Weinberg)
Advances in Nuclear Science and Technology, Vol. 4(P. L. Hofmann)
Principles of Radiation Protection(Newton Underwood)
Nuclear Reactor Materials(T. W. Evans)

Measurement of the Neutron Fission and Capture Cross Sections for ²³³U in the Energy Region 0.4 to 2000 eV

L. W. Weston, R. Gwin, and G. deSaussure, R. R. Fullwood and R. W. Hockenbury

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE68-A19361

Absolute Fission Rate Measurements with Solid-State Track Recorders

Raymond Gold and Roland J. Armani, James H. Roberts

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 13-32

Technical Paper / dx.doi.org/10.13182/NSE68-A19362

Neutron-Wave Propagation Through a Crystalline Moderator-II: Graphite

Feroz Ahmed, P. S. Grover and L. S. Kothari

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 33-38

Technical Paper / dx.doi.org/10.13182/NSE68-A19363

Effective Source Strength for Arbitrarily Anisotropic Neutron Scattering in Infinite Medium

E. İnönü and A. İ. Usseli

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 39-44

Technical Paper / dx.doi.org/10.13182/NSE68-A19364

A Variational Multichannel Space-Time Synthesis Method for Nonseparable Reactor Transients

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 45-56

Technical Paper / dx.doi.org/10.13182/NSE68-A19365

Positivity Theorems for the Discrete Form of the Multigroup Diffusion Equations

Reimar Froehlich

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 57-66

Technical Paper / dx.doi.org/10.13182/NSE68-A19366

Numerical Comparison of Diffusion-Like Transport Approximations for Very Fast Neutrons

L. B. Freeman and H. W. Ryals

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 67-75

Technical Paper / dx.doi.org/10.13182/NSE68-A19367

A New Derivation of Discrete Ordinate Approximations

Stanley Kaplan

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 76-82

Technical Paper / dx.doi.org/10.13182/NSE68-A19368

MS_n, A New Approach to Neutron Transport Analysis

Shoichiro Nakamura

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 83-86

Technical Note / dx.doi.org/10.13182/NSE68-A19369

Geometric Buckling of Polygonal Reactors

Raymond L. Murray, Thomas J. Hirons, Raymond J. Reith, and Owen J. Smith

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Pages 86-87

Technical Note / dx.doi.org/10.13182/NSE68-A19370

The Determination of the Eigenvalues and Eigenfunctions Corresponding to Azimuthal Harmonics of a Reactor Having RZ Symmetry

F. D. Judge

Nuclear Science and Engineering / Volume 34 / Number 1 / October 1968 / Page 87

Technical Note / dx.doi.org/10.13182/NSE68-A19371

Number 2

Table of Contents
The Art of Computer Programming(William J. Worlton)
Plutonium Handbook(Louis D. Kirkbride)
Radiation Dosimetry: Fundamentals(J. E. Turner)
Comments on “Theoretical and Experimental Criteria for Nonlinear Reactor Stability”(Joseph E. Kalinowski)
Reply to “Comments on ‘Theoretical and Experimental Criteria for Nonlinear Reactor Stability’”(Elias P. Gyftopoulos)

On the Calculation of Neutron Inelastic Scattering Cross Sections

Mark Goldsmith

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 93-97

Technical Paper / dx.doi.org/10.13182/NSE68-A19534

An Experimental Investigation of Spatial Effects on the Neutron Fluctuation Spectra of a Large Reactor

A. R. Buhl, S. H. Hanauer, N. P. Baumann

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 98-103

Technical Paper / dx.doi.org/10.13182/NSE68-A19535

Thermal-Neutron Flux Generation by High-Energy Protons

W. A. Coleman, R. G. Alsmiller, Jr.

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 104-113

Technical Paper / dx.doi.org/10.13182/NSE68-A19536

Experimental Evaluation of Minima in the Total Neutron Cross Sections of Several Shielding Materials

E. A. Straker

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 114-121

Technical Paper / dx.doi.org/10.13182/NSE68-A19537

Space-Angle Energy-Time-Dependent Neutron Transport in a Homogeneous Slab by the j_N Method

T. Asaoka

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 122-133

Technical Paper / dx.doi.org/10.13182/NSE68-A19538

Solution to the Neutron Transport Equation for an Infinite Cylinder by Fourier Series

W. L. Hendry

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 134-147

Technical Paper / dx.doi.org/10.13182/NSE68-A19539

Transient Temperature Distribution in a Reactor Channel with Cylindrical Fuel Rods and Compressible Coolant

Heinz Vollmer

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 148-157

Technical Paper / dx.doi.org/10.13182/NSE68-A19540

Numerical Studies of Combined Space-Time Synthesis

J. B. Yasinsky

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 158-168

Technical Paper / dx.doi.org/10.13182/NSE68-A19541

Spectrum of Gamma Rays Emitted by a Stainless Steel Clad, Pool-Type Reactor (BSR-II)

G. T. Chapman, W. R. Burrus

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 169-180

Technical Paper / dx.doi.org/10.13182/NSE68-A19542

The Construction of Statistical Neutron Resonances

M. W. Dyos

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 181-188

Technical Paper / dx.doi.org/10.13182/NSE68-A19543

Cross Flow and Mixing of Water Between Semiopen Channels

G. Hetsroni, J. Leon,, M. Hakim

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 189-193

Technical Paper / dx.doi.org/10.13182/NSE68-A19544

Additional Conditions to the Neutron Multiplication Method of Reactivity Determination

S. Chwaszczewski

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 194-195

Technical Note / dx.doi.org/10.13182/NSE68-A19545

Revised Value for the Thermal-Neutron Capture Cross Section of Deuterium

Janet S. Merritt, J. G. V. Taylor, A. W. Boyd

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 195-196

Technical Note / dx.doi.org/10.13182/NSE68-A19546

On the Expansion of Experimental Functions in Series of Descending Exponentials of Real Argument

Fr. J. Servais

Nuclear Science and Engineering / Volume 34 / Number 2 / November 1968 / Pages 196-197

Technical Note / dx.doi.org/10.13182/NSE68-A19547

Number 3

Table of Contents
GANDY(S. C. Cohen, P. K. Koch)
Dictionary of Russian Technical and Scientific Abbreviations(Francois Kertesz)
Modal Approximations: Theory and an Application to Reactor Physics(Paul F. Zweifel)
Nuclear Chemistry(Curtis E. Bemis, Jr. and Richard L. Hahn)

A Study of the Release of Radioactive Metallic Isotopes from High-Temperature Gas-Cooled Reactors

J. Appel and B. Roos

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 201-213

Technical Paper / dx.doi.org/10.13182/NSE68-A21086

Removal of Water and Carbon Dioxide from Helium Coolants by Molecular Sieves

Charles D. Scott

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 214-223

Technical Paper / dx.doi.org/10.13182/NSE68-A21087

Inelastic Scattering of Thermal Neutrons in Graphite

F. Carvalho

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 224-236

Technical Paper / dx.doi.org/10.13182/NSE68-A21088

Criticality Measurements on Nearly Homogeneous Enriched Uranium-Graphite Systems

James P. Phelps and Eugene V. Weinstock

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 237-250

Technical Paper / dx.doi.org/10.13182/NSE68-A21089

Analysis of Brookhaven ²³⁵U-Graphite Critical Experiments

Bal Raj Sehgal

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 251-262

Technical Paper / dx.doi.org/10.13182/NSE68-A21090

Analysis of a Set of Critical Homogeneous U-H₂O Spheres

Alan Staub, D. R. Harris, and Mark Goldsmith

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 263-274

Technical Paper / dx.doi.org/10.13182/NSE68-A21091

A Pulsed-Neutron Investigation of the Effect of Temperature on the Decay of a Thermal-Neutron Population in H₂O Ice

Ernest G. Silver

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 275-284

Technical Paper / dx.doi.org/10.13182/NSE68-A21092

Streaming Effects and Collision Probabilities in Lattices

P. Benoist

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 285-307

Technical Paper / dx.doi.org/10.13182/NSE68-3

The Calculation of Neutron Flux Ratios in Critical Systems by the Indirect Variational Method

G. C. Pomraning

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 308-312

Technical Paper / dx.doi.org/10.13182/NSE68-A21094

An Analysis of Methods for Calculating Spatially Dependent Neutron Slowing Down Distributions

Harvey J. Amster

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 313-327

Technical Paper / dx.doi.org/10.13182/NSE68-A21095

Linear Energy Transformation for Gamma-Ray Monte Carlo Calculations

A. B. Chilton

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 328-329

Technical Note / dx.doi.org/10.13182/NSE68-A21096

Evaluation of Neutron Absorption Rates by Activation Measurements of Spectral Indexes

F. Pistella

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 329-331

Technical Note / dx.doi.org/10.13182/NSE68-A21097

Self-Shielding Factors for Scattering Dominant Neutron Resonances

W. H. Roach

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 331-332

Technical Note / dx.doi.org/10.13182/NSE68-A21098

Sensitivity of Neutron Transport in Oxygen to Various Cross-Section Sets

E. A. Straker

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 332-336

Technical Note / dx.doi.org/10.13182/NSE68-A21099

Applications of a Macroscopic Formulation of Transport Theory

W. Pfeiffer and J. L. Shapiro

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 336-339

Technical Note / dx.doi.org/10.13182/NSE68-A21100

Overlapping Group Methods with Discontinuous Trial Functions

Martin Becker

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 339-341

Technical Note / dx.doi.org/10.13182/NSE68-A21101

On the Use of Different Radial Trial Functions in Different Axial Zones of a Neutron Flux Synthesis Computation

E. L. Wachspress

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 342-343

Technical Note / dx.doi.org/10.13182/NSE68-A21102

Asymmetric Discontinuities in Synthesis Techniques for Initial-Value Problems

Martin Becker

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 343-344

Technical Note / dx.doi.org/10.13182/NSE68-A21103

Verification of a Xenon Spatial Stability Criterion

Richard J. Hooper, Roger A. Rydin, and Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 34 / Number 3 / December 1968 / Pages 344-346

Technical Note / dx.doi.org/10.13182/NSE68-A21104