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Volume 31

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Number 1

Table of Contents
Proceedings of Symposium on Criticality Control of Fissile Materials(E. R. Woodcock)
Fast Reactor Technology: Plant Design(Eugene R. Astley)
Importance of The Adjoint Function(J. Wallace Webster)
Comment on Carlvik's Paper on Dancoff Correction in Lattices(P. J. Fulford)
On the Connection Between Absorption and Anisotropy of Scattering in Neutron Transport Theory(A. I. Usseli, P. F. Zweifel)
Virtual Limitation of Variational Principle(S. R. Dwivedi)

Drop Extraction Between Liquid Metals and Fused Salts

Donald R. Olander

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 1-18

Technical Paper / dx.doi.org/10.13182/NSE68-A18003

Experimental Studies of Microparameters of Clusters of Seven Nuclear Superheat Reactor Fuel Rods

J. T. Wajima, H. Yamamoto, H. Kikuchi, T. Ohnishi, S. Kobayashi

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 19-31

Technical Paper / dx.doi.org/10.13182/NSE68-A18004

Theoretical Analyses of Homogeneous Plutonium Critical Experiments

C. R. Richey

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 32-39

Technical Paper / dx.doi.org/10.13182/NSE68-A18005

Criticality of Heterogeneous Arrays Undergoing Dissolution

C. R. Richey

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 40-48

Technical Paper / dx.doi.org/10.13182/NSE68-A18006

Age Measurements in ThO₂-D₂O-H₂O Lattices

Donald M. Roberts, William G. Pettus

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 49-56

Technical Paper / dx.doi.org/10.13182/NSE68-A18007

A Comparison of Heterogeneous Nuclear-Reactor Lattice Theory with Experiment

W. E. Graves, F. D. Benton, R. M. Satterfield

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 57-66

Technical Paper / dx.doi.org/10.13182/NSE68-A18008

On the Stability of Nonlinear Space-Dependent Reactor Kinetics

William E. Kastenberg, Paul L. Chambré

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 67-79

Technical Paper / dx.doi.org/10.13182/NSE68-A18009

On the Use of Dual Variational Principles for the Estimation of Error in Approximate Solutions of Diffusion Problems

J. B. Yasinsky, S. Kaplan

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 80-90

Technical Paper / dx.doi.org/10.13182/NSE68-A18010

Flux Synthesis Using Green's Function in Two-Dimensional Group Diffusion Equations

Keisuke Kobayashi

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 91-101

Technical Paper / dx.doi.org/10.13182/NSE68-A18011

Neutron Thermalization in Heavy Gas with Nonuniform Temperature Distribution

Pekka Jauho, Antti Virjo

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 102-109

Technical Paper / dx.doi.org/10.13182/NSE68-A18012

Albedo and Milne's Problem for Thermal Neutrons

S. Pahor

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 110-116

Technical Paper / dx.doi.org/10.13182/NSE68-A18013

A Boltzmann Integral Equation Treatment of Neutron Resonance Absorption in Reactor Lattices

E. E. Lewis, F. T. Adler

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 117-126

Technical Paper / dx.doi.org/10.13182/NSE68-A18014

Transport Error Bounds Via P_N Approximations

James A. Davis

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 127-146

Technical Paper / dx.doi.org/10.13182/NSE68-A18015

A Study Concerning the Number of “Effective” Equally Limiting Hot Channels in a Reactor with a Cosine Power Distribution

F. D. Judge

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 147-148

Technical Note / dx.doi.org/10.13182/NSE68-A18016

Effects of Voids on Diffusion Length and Streaming of Neutrons in Water

Naeem Ahmad Khan, S. M. Kabir

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 148-149

Technical Note / dx.doi.org/10.13182/NSE68-A18017

Neutron Absorption Cross Section of ²³⁷U

W. R. Cornman, E. J. Hennelly, C. J. Banick

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 149-152

Technical Note / dx.doi.org/10.13182/NSE68-A18018

The Thermal-Neutron Capture Cross Section of Cadmium

J. W. Meadows

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 152-153

Technical Note / dx.doi.org/10.13182/NSE68-A18019

Neutron Spectra in Thin Polyethylene Slabs

S. B. Armstrong

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 153-155

Technical Note / dx.doi.org/10.13182/NSE68-A18020

Neglect of the Energy-Angle Correlation in Nonscattering Neutron Emission Reactions

S. T. Perkins

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 156-157

Technical Note / dx.doi.org/10.13182/NSE68-A18021

On Solving Certain Group-Diffusion Problems in Finite-Difference Form

Melvin Tobias

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 157-160

Technical Note / dx.doi.org/10.13182/NSE68-A18022

Time-Dependent Variational Theory

Jeffery Lewins

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 160-163

Technical Note / dx.doi.org/10.13182/NSE68-A18023

The Effect of Source Distribution on Neutron Resonance Integrals

A. C. deLoach and J. E. Suich

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 163-167

Technical Note / dx.doi.org/10.13182/NSE68-A18024

A Reformulation of the Doppler Effect in Resonant Neutron Capture

W. G. Pettus

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 168-169

Technical Note / dx.doi.org/10.13182/NSE68-A18025

Number 2

Table of Contents
Reflections on Big Science(Manson Benedict)
Erwin Schrödinger: An Introduction to His Writings(William G. Pollard)
The Technical Applications of Radioactivity(Ralph T. Overman)
Proceedings of a Symposium on Neutron Monitoring for Radiological Protection(Edward J. Vallario, James E. McLaughlin)

Study of Lithium Mobility in Irradiated Silicon

Walter A. Hackler, Chihiro Kikuchi

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 175-182

Technical Paper / dx.doi.org/10.13182/NSE68-A18229

Geometry and Barrier Attenuation of Cobalt-60 Gamma Rays by a Vertical Steel Slab

G. E. Plummer

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 183-190

Technical Paper / dx.doi.org/10.13182/NSE68-A18230

A Study of Fission-Neutron Spectra with High-Energy Activation Detectors. Part II: Fission Spectra

James A. Grundl

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 191-206

Technical Paper / dx.doi.org/10.13182/NSE68-A18231

The Energy Spectrum of Fast Neutrons Slowing Down from a Fission Source in a Homogeneous Medium

T. E. Murley, I. Kaplan

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 207-214

Technical Paper / dx.doi.org/10.13182/NSE68-A18232

Cross-Spectral Density Measurements in a Coupled-Core Reactor

Richard A. Hendrickson, Glenn Murphy

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 215-221

Technical Paper / dx.doi.org/10.13182/NSE68-A18233

Analysis of Pulsed Fast-Neutron Spectra in Multiplying Assemblies

J. D. Jenkins, P. B. Daitch

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 222-233

Technical Paper / dx.doi.org/10.13182/NSE68-A18234

The Statistical Estimation of Thermal-Neutron Cross Sections

J. L. Cook, A. L. Wall

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 234-240

Technical Paper / dx.doi.org/10.13182/NSE68-A18235

Measurement of ¹³⁵I Yield Ratios and Fission-Product Cross Sections in the Advanced Reactivity Measurement Facilities

R. G. Nisle, I. E. Stepan

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 241-246

Technical Paper / dx.doi.org/10.13182/NSE68-A18236

Low-Flux Measurement of ²³⁵U Epicadmium Capture-to-Fission Ratio

W. C. Redman, M. M. Bretscher

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 247-253

Technical Paper / dx.doi.org/10.13182/NSE68-A18237

Neutron Scattering from Light Water

J. R. Beyster

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 254-271

Technical Paper / dx.doi.org/10.13182/NSE68-A18238

Energy Optimal Xenon Shutdown

Jeffrey Lewins, Gordon R. Woodcock, Theodore J. Williamson, Albert L. Babb

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 272-281

Technical Paper / dx.doi.org/10.13182/NSE68-A18239

Monte Carlo Analysis of Nuclear Reactor Fluctuation Models

Burt A. Zolotar

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 282-294

Technical Paper / dx.doi.org/10.13182/NSE68-A18240

Monoenergetic Critical Parameters and Decay Constants for Small Homogeneous Spheres and Thin Homogeneous Slabs

I. Carlvik

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 295-303

Technical Paper / dx.doi.org/10.13182/NSE31-295

Numerical Solution of the Time-Dependent Multigroup Diffusion Equations

J. Barclay Andrews, II, K. F. Hansen

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 304-313

Technical Paper / dx.doi.org/10.13182/NSE68-A18242

Comparison of Neutron-Transport and Diffusion Theories of Isotropic Scattering

P. S. Grover, L. S. Kothari, A. K. Ghatak

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 314-317

Technical Paper / dx.doi.org/10.13182/NSE68-A18243

Accuracy of Transport Theory Calculations of an Anisotropic Neutron Flux

Pekka Jauho, Heikki Kalli

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 318-324

Technical Paper / dx.doi.org/10.13182/NSE68-A18244

A Strategy for the Application of Space-Angle Synthesis to Practical Problems in Neutron Transport

M. Natelson

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 325-336

Technical Paper / dx.doi.org/10.13182/NSE68-A18245

Effect of Property Variation on the Turbulent Flow of Gases in Tubes: The Thermal Entry

P. M. Magee, D. M. McEligot

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 337-341

Technical Note / dx.doi.org/10.13182/NSE68-A18246

Total Cross Sections of Na, K, and Ca for 14-MeV Neutrons

F. Guarrini, A. Luches, G. Pauli, G. Poiani

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 341-343

Technical Note / dx.doi.org/10.13182/NSE68-A18247

Absolute Neutron Yields from Thick Target ^NATC(α,n)

R. L. Macklin, J. H. Gibbons

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Page 343

Technical Note / dx.doi.org/10.13182/NSE68-A18248

Comparison of Beryllium Photoneutron Decay Sets Using Experimental SNAP Data

Eric H. Ottewitte

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 343-346

Technical Note / dx.doi.org/10.13182/NSE68-A18249

David T. Goldman

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 346-349

Technical Note / dx.doi.org/10.13182/NSE68-A18250

The Application of Synthesis Techniques to the Calculations of Three-Dimensional Reactivity-Coefficient Distributions

J. L. Bear, F. D. Judge, E. R. Venerus

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 349-353

Technical Note / dx.doi.org/10.13182/NSE68-A18251

Anomalies Arising from the Use of Adjoint Weighting in a Collapsed Group-Space Synthesis Model

J. B. Yasinsky, S. Kaplan

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 354-358

Technical Note / dx.doi.org/10.13182/NSE68-A18252

Flux Tilting in a Two-Zone Reactor

D. E. Jeffers, K. Hall

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 358-359

Technical Note / dx.doi.org/10.13182/NSE68-A18253

Number 3

Table of Contents
Mathematical Theory of Elementary Particles(Kerson Huang)
Unified Theory of Nuclear Models and Forces(Benjamin F. Bayman)
Lie Groups for Pedestrians(Malcolm Harvey)
Linear Transport Theory(George I. Bell)
Introduction to Quantum Theory of Scattering(A. E. S. Green, B. S. Thomas)
The Theory of Neutron Slowing Down in Nuclear Reactors(E. M. Gelbard)
Neutron Noise, Waves and Pulse Propagation(Charles Erwin Cohn)
Radioisotope Measurement Applications in Engineering(J. Kohl)
Modern Control Systems(J. A. Thie)

S_∞ Neutron Transport Theory in Plane Geometry

J. Mennig, J. T. Marti

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 365-368

Technical Paper / dx.doi.org/10.13182/NSE68-A17580

An Improved Method for Calculating Rethermalization Neutron Cross Sections

Roger W. Carlson and K. F. Hansen

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 369-376

Technical Paper / dx.doi.org/10.13182/NSE68-A17581

An Activation Experiment to Determine the Coefficients in the Laguerre Expansion of Perturbed Thermal-Neutron Spectra

Jacek Jedruch

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 377-387

Technical Paper / dx.doi.org/10.13182/NSE68-A17582

Intermediate Neutron Resonance Absorption in Heterogeneous Systems

Yukio Ishiguro and Hideki Takano

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 388-395

Technical Paper / dx.doi.org/10.13182/NSE68-A17583

Adjusting Absorption Cross Sections in Transport Calculations to Achieve Specified Region Capture Integrals

Donald S. Rampolla

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 396-414

Technical Paper / dx.doi.org/10.13182/NSE68-A17584

Effective Resonance Integrals of Separated Tungsten Isotopes from Reactivity Measurements

Donald F. Shook and Donald Bogart

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 415-430

Technical Paper / dx.doi.org/10.13182/NSE68-A17585

Determination of Dilute ¹⁸⁶W and ¹⁸⁴W Resonance Integrals by Activation

Clarence R. Pierce and Donald F. Shook

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 431-439

Technical Paper / dx.doi.org/10.13182/NSE68-A17586

Variances and Covariances of Neutron and Precursor Populations in Time-Varying Reactions

W. G. Clarke, D. R. Harris, M. Natelson, J. F. Walter

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 440-457

Technical Paper / dx.doi.org/10.13182/NSE68-A17587

A Generalized Formulation of Point Nuclear Reactor Kinetics Equations

Martin Becker

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 458-464

Technical Paper / dx.doi.org/10.13182/NSE68-A17588

On Transient Digital Control of Large Nuclear Power Reactors

W. Ciechanowicz

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 465-473

Technical Paper / dx.doi.org/10.13182/NSE68-A17589

On the On-Line Statistical Identification of Nuclear Power Reactor Dynamics

W. Ciechanowicz and S. Bogumil

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 474-483

Technical Paper / dx.doi.org/10.13182/NSE68-A17590

Neutron-Wave Propagation Through a Crystalline Moderator-I: Beryllium

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

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 484-491

Technical Paper / dx.doi.org/10.13182/NSE68-A17591

The Application of Track-Length Distribution Biasing in Monte Carlo Deep-Penetration Calculations

R. H. Karcher, R. C. Erdmann, O. C. Baldonado

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 492-499

Technical Paper / dx.doi.org/10.13182/NSE68-A17592

The Use of Self-Optimized Exponential Biasing in Obtaining Monte Carlo Estimates of Transmission Probabilities

Leo B. Levitt

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 500-504

Technical Paper / dx.doi.org/10.13182/NSE68-A17593

The Synthesis Method of Uncertainty Analysis in Nuclear Reactor Thermal Design

Henri Fenech and Henri M. Guéron

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 505-512

Technical Paper / dx.doi.org/10.13182/NSE68-A17594

Thermal-Neutron-Induced Defects in n-Type Cadmium Telluride

Charles Barnes and Chihiro Kikuchi

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 513-520

Technical Paper / dx.doi.org/10.13182/NSE68-A17595

Reactor Organic Coolants III: Temperature, Intensity and Post irradiation Effects in the Electron Radiolysis of Meta-Terphenyl

Donna Wuschke and M. Tomlinson

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 521-530

Technical Paper / dx.doi.org/10.13182/NSE68-A17596

On the Dispersion of Fission Products from Laminar Streams in Open- and Closed-Loop Conduits

E. R. Venerus and M. N. Ozisik

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 531-539

Technical Paper / dx.doi.org/10.13182/NSE68-A17597

An Iterative Method for Determination of a Minimal Eigenvalue

G. K. Kristiansen

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Page 540

Technical Note / dx.doi.org/10.13182/NSE68-A17598

The Temperature Dependence of the Effective Resonance Integral of Thorium Oxide Rods

J. A. Kadlecek, F. C. Schoenig, K. S. Quisenberry

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 541-544

Technical Note / dx.doi.org/10.13182/NSE68-A17599

Reactor Neutron Cross Sections for Some (n, γ) Reactions

R. S. Tilbury and Henry H. Kramer

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 545-546

Technical Note / dx.doi.org/10.13182/NSE68-A17600

Time-of-Flight Effects in Pulsed-Neutron Measurements

Glenn A. Price and Henry H. Windsor

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 547-548

Technical Note / dx.doi.org/10.13182/NSE68-A17601

Low-Enrichment Uranium-Metal Exponential Experiments

C. G. Chezem and R. G. Steinke

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Page 549

Technical Note / dx.doi.org/10.13182/NSE68-A17602

Acceleration of the Convergence of Successive Block Overrelaxation by Use of an Improved Block Pattern in the Solution of the Equation for Transient Heat Conduction

B. Kaplan and K. D. Wright

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Page 550

Technical Note / dx.doi.org/10.13182/NSE68-A17603

Metal-Water Explosions

Fredrick E. Brauer, N. Wayne Green, Russell B. Mesler

Nuclear Science and Engineering / Volume 31 / Number 3 / March 1968 / Pages 551-554

Technical Note / dx.doi.org/10.13182/NSE68-A17604