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Volume 37

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Number 1

Table of Contents

Solution of the One-Velocity Transport Equation in Terms of Synthetic Kernels

Herbert Henryson, II, David S. Selengut

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 1-18

Technical Paper / dx.doi.org/10.13182/NSE69-A20894

A Stability Criterion for Space-Dependent Nuclear-Reactor Systems with Variable Temperature Feedback

William E. Kastenberg

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 19-29

Technical Paper / dx.doi.org/10.13182/NSE69-A20895

The Metastatic Method in Nuclear Reactor Core Kinetics Calculations

A. Galati

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 30-40

Technical Paper / dx.doi.org/10.13182/NSE69-A20896

A Discrete Stochastic Model for Neutron Moderation

T. J. Williamson, R. W. Albrecht

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 41-58

Technical Paper / dx.doi.org/10.13182/NSE69-A20897

Numerical Results of Interfacial Effects on Neutron Waves

O. C. Baldonado, R. C. Erdmann

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 59-65

Technical Paper / dx.doi.org/10.13182/NSE69-A20898

The Temperature Dependence of Epithermal Neutron Capture and Fission in Uranium-235 Dioxide

F. C. Schoenig, Jr., F. A. White, F. Feiner

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 66-84

Technical Paper / dx.doi.org/10.13182/NSE69-A20899

A Theory of Pulsed Neutron Experiments in Polycrystalline Media

Robert Conn, Noel Corngold

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 85-93

Technical Paper / dx.doi.org/10.13182/NSE69-A20900

Analysis of Pulsed Neutron Experiments in Polycrystalline Media Using a Model Kernel

Robert Conn, Noel Corngold

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 94-103

Technical Paper / dx.doi.org/10.13182/NSE69-A20901

Time-Dependent Analysis of Subcritical and Nonmultiplying Systems

P. d'Oultremont

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 104-110

Technical Paper / dx.doi.org/10.13182/NSE69-A20902

Fast Neutron Spectrum for a Subcritical Section of a Homogeneous ²³⁵U-Polyethylene Critical Assembly

S. C. Cohen, R. A. Moore, J. C. Young, J. L. Russell, Jr.

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 111-126

Technical Paper / dx.doi.org/10.13182/NSE69-A20903

Thermal-Neutron Diffusion in Aqueous Absorbing Solutions

A. J. H. Goddard, P. W. Johnson

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 127-136

Technical Paper / dx.doi.org/10.13182/NSE69-A20904

Neutron Radiative Capture and Transmission Measurements of W and Zr Isotopes in the keV Region

Z. M. Bartolome, R. W. Hockenbury, W. R. Moyer, J. R. Tatarczuk, R. C. Block

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 137-156

Technical Paper / dx.doi.org/10.13182/NSE69-A20905

Prediction of Tube Wall Temperatures with Axial Variation of Heating Rate and Gas Property Variation

C. A. Bankston, D. M. McEligot

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 157-162

Technical Paper / dx.doi.org/10.13182/NSE69-A20906

Reactor Control Using a New Multivariable Design Technique

Charles R. Slivinsky, Lynn E. Weaver

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 163-166

Technical Note / dx.doi.org/10.13182/NSE69-A20907

Escape Probabilities in Close-Packed Lattices

R. S. Carlsmith, D. Steiner

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 166-167

Technical Note / dx.doi.org/10.13182/NSE69-A20908

The Thermal Neutron Diffusion Length in Liquid Terphenyl

A. J. H. Goddard, G. E. B. Tremeer

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 167-169

Technical Note / dx.doi.org/10.13182/NSE69-A20909

Number 2

Table of Contents
Comment on “A Space-Dependent Reactor-Noise Formulation Utilizing Modal Expansions”(R. W. Albrecht)
Further Comment on ‘A Space-Dependent Reactor-Noise Formulation Utilizing Modal Expansions’(R. A. Danofsky)
On the Stabilizing Effect of Delayed Neutrons(Sevim Tan)
“Reply to ‘On the Stabilizing Effect of Delayed Neutrons’”(Henri B. Smets)
Introduction to Nuclear Theory(Richard K. Osborn)

Stability and Stationarity of a Reactor as a Stochastic Process with Feedback

D. R. Harris, V. Prescop

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 171-179

Technical Paper / dx.doi.org/10.13182/NSE69-A20675

A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation

M. V. Speight

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 180-185

Technical Paper / dx.doi.org/10.13182/NSE69-A20676

Discrete Kinetics for Periodically Pulsed Fast Reactors

G. Blaesser, J. A. Larrimore

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 186-191

Technical Paper / dx.doi.org/10.13182/NSE69-A20677

Measurements of the Normalization Integral and the Spatial Distribution of the Importance of Fission Neutrons

R. A. Karam

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 192-197

Technical Paper / dx.doi.org/10.13182/NSE69-A20678

Coherent Neutron Scattering from Polycrystalline Graphite

Hiroshi Takahashi

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 198-215

Technical Paper / dx.doi.org/10.13182/NSE69-A20679

The Effect of Axial Heat Conduction on the Thermal Development of a Heat-Generating Fluid

M. E. Nelson, J. H. Rust, F. A. Iachetta

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 216-223

Technical Paper / dx.doi.org/10.13182/NSE69-A20680

Kinetic Energy Spectra of Foil-Transmitted Fission Fragments of ²⁵²Cf

L. Bridwell, Shawn Bucy

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 224-227

Technical Paper / dx.doi.org/10.13182/NSE69-A20681

The Thermal-Neutron Capture Cross Section and Resonance Integral of ²⁵²Cf

J. Halperin, C. E. Bemis, R. E. Druschel, J. R. Stokely

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 228-231

Technical Paper / dx.doi.org/10.13182/NSE69-A20682

Transmission Measurement of the ²⁵²Cf Fission Neutron Spectrum

L. Green

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 232-242

Technical Paper / dx.doi.org/10.13182/NSE69-A20683

Neutron Transport for Anisotropic Scattering in Adjacent Half-Spaces. I. Theory

N. J. McCormick

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 243-251

Technical Paper / dx.doi.org/10.13182/NSE69-A20684

Neutron Transport for Anisotropic Scattering in Adjacent Half-Spaces. II. Numerical Results

N. J. McCormick, R. J. Doyas

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 252-261

Technical Paper / dx.doi.org/10.13182/NSE69-A20685

Analysis of Fuel-Block Worth Measurements for a Small Fast Assembly in a Three-Dimensional Configuration

D. A. Sargis, S. C. Cohen, R. A. Moore

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 262-270

Technical Paper / dx.doi.org/10.13182/NSE69-A20686

Theoretical Neutron Production from Hydrogen Isotope Reactions

J. A. Halbleib, Sr., M. R. Scott

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 271-277

Technical Paper / dx.doi.org/10.13182/NSE69-A20687

A New Non-Multigroup Adjoint Monte Carlo Technique

Leo B. Levitt, Jerome Spanier

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 278-287

Technical Paper / dx.doi.org/10.13182/NSE69-A20688

The Synthetic Method as Applied to the S_n Equations

E. M. Gelbard, L. A. Hageman

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 288-298

Technical Paper / dx.doi.org/10.13182/NSE69-A20689

Determination of Reactivity of a Subcritical System

K. S. Ram, R. E. Uhrig

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 299-300

Technical Note / dx.doi.org/10.13182/NSE69-A20690

Resonance Neutron Absorption in a Foil in a Plate-Type Lattice

Kerry D. Dance

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 300-304

Technical Note / dx.doi.org/10.13182/NSE69-A20691

Calculation of the Energy Deposited by Nucleons in a Spherical Phantom and Comparison with Experiment

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

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 304-306

Technical Note / dx.doi.org/10.13182/NSE69-A20692

Exponential Experiments with a UO₂-Light Water Lattice Containing Air Bubbles

Kiyosi Kobayasi, Yuuki Hachiya, Yoshihiro Iida

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 306-308

Technical Note / dx.doi.org/10.13182/NSE69-A20693

Effect of Infinite Reflectors on Critical Slab Thickness

N. J. McCormick, R. J. Doyas

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 308-311

Technical Note / dx.doi.org/10.13182/NSE69-A20694

Determination of Stability Domains in Space Dependent Reactor Dynamics

William E. Kastenberg, Raymond M. Crawford

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 311-316

Technical Note / dx.doi.org/10.13182/NSE69-A20695

Temperature Noise in Low-Power Reactors

Keiichi Saito

Nuclear Science and Engineering / Volume 37 / Number 2 / August 1969 / Pages 316-321

Technical Note / dx.doi.org/10.13182/NSE69-A20696

Number 3

Table of Contents
PIGG(T. Kulikowska, J. O. Berg, G. E. Fladmark, O. P. Tverbakk)
ETOX: A Code to Calculate Group Constants for Nuclear Reactor Calculations(R. E. Schenter, J. L. Baker, R. B. Kidman)
1DX: A One-Dimensional Cross Section Generating Code(R. W. Eardie, W. W. Little, Jr.)
NØWIG(J. B. Yasinsky)
Nuclear and Particle Physics(Robert W. Richardson)

Heat Conduction in Reactor Fuel Elements

G. Hetsroni, E. Wacholder, S. Haber

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 329-336

Technical Paper / dx.doi.org/10.13182/NSE69-A19109

Calculation of the Radiation Hazard at Supersonic Aircraft Altitudes Produced by an Energetic Solar Flare

T. W. Armstrong, R. G. Alsmiller, Jr., J. Barish

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 337-342

Technical Paper / dx.doi.org/10.13182/NSE69-A19110

Analysis of Neutron Focusing by Conical Tubes and its Possible Applications

T. Shimooke

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 343-357

Technical Paper / dx.doi.org/10.13182/NSE69-A19111

Neutron-Wave Propagation in Crystalline Moderators—IV: A Two-Group Study

Ashok Kumar, F. Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 358-367

Technical Paper / dx.doi.org/10.13182/NSE69-A19112

Slow-Neutron Scattering by Molecular Liquids

Ashok K. Agrawal, Sidney Yip

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 368-379

Technical Paper / dx.doi.org/10.13182/NSE69-A19113

Input-Noise Source of At-Power Reactors with Temperature Feedback Effect

Keiichi Saito

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 380-396

Technical Paper / dx.doi.org/10.13182/NSE69-A19114

Energy-Dependent Neutron Transport Theory Near a Temperature Discontinuity

Eugene C. Gritton, A. Leonard

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 397-409

Technical Paper / dx.doi.org/10.13182/NSE69-A19115

Monte Carlo Integration of the Adjoint Neutron Transport Equation

Bo Eriksson, Claes Johansson, Martin Leimdorfer, M. H. Kalos

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 410-422

Technical Paper / dx.doi.org/10.13182/NSE69-A19116

Space-Energy Flux Synthesis in Transport Theory

M. J. Lancefield

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 423-442

Technical Paper / dx.doi.org/10.13182/NSE69-A19117

Stabilizing Control Functions

Gary M. Sandquist

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 443-450

Technical Paper / dx.doi.org/10.13182/NSE69-A19118

Pressurized Water Reactor Optimal Core Management and Reactivity Profiles

Michel Mélice

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 451-477

Technical Paper / dx.doi.org/10.13182/NSE69-A19119

An Evaluation of the Activation Cross Section of ¹⁵¹Eu

F. V. Orestano, F. Pistella

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 478-480

Technical Note / dx.doi.org/10.13182/NSE69-A19120