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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE69-A20696

Number 3

Table of Contents
ETOX: A Code to Calculate Group Constants for Nuclear Reactor Calculations (R. E. Schenter, J. L. Baker, R. B. Kidman)
PIGG (T. Kulikowska, J. O. Berg, G. E. Fladmark, O. P. Tverbakk)
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE69-A19120