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Volume 21

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Number 1

Table of Contents
Activation Cross Section for Krypton-83m(S. L. Ruby, R. Ellefson)
Modification to Prescription for (k β/l) Pulsing(Lawrence Ruby)
Empirical Gamma-Ray Albedo Formula(T. H. Jones, N. E. Scofield, W. J. Gurney)
A Note on the Analysis of Pulsed Neutron Shutdown Measurements(S. K. Wallace)
First-Collision Probability of an Infinite Rectangular Cylinder(N. J. McCormick)
Moderator Scattering and Flux Depression Near Resonances(Paul F. Gast)
Comparison of Critical and Subcritical ρ^{28 Measurements}(J. M. Døderlein, J. A. Thomassen, T. H. Johansen)
Modern Digital Circuits(Dan McMillin)
The Two-Nucleon Interaction(Herman Feshbach)
Aqueous Reprocessing Chemistry for Irradiated Fuels(Raymond E. Blanco)
Handbook of Applied Instrumentation(Leonard Reiffel)
The Theory of Branching Processes(George I. Bell)
Power Reactor Experiments(Arthur W. Flynn)
Applications of Neutron Diffraction in Chemistry(George I. Bell)
Advances in Nuclear Science and Technology, Vols. 1 and 2(Harold Etherington)
Development of Fueled Graphite Containing Pyrolytic-Carbon-Coated Carbide Particles for Nonpurged, Gas-Cooled Reactor Systems(F. L. Carlsen Jr., E. S. Bomar, W. R. Harms)

Fission-Product Release from Monogranular UC₂ Particles

L. R. Zumwalt, P. E. Gethard, E. E. Anderson

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE65-A21008

Influence of Internal Thermal Radiation on Heat Transfer in UO₂ Fuel Elements

R. Viskanta

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 13-19

Technical Paper / dx.doi.org/10.13182/NSE65-A21009

The Thermal Neutron-Capture Cross Section and Resonance-Capture Integral of Ru¹⁰⁶

R. D. Werner, T. A. Eastwood

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 20-25

Technical Paper / dx.doi.org/10.13182/NSE65-A21010

Visible and Infrared Absorption Spectra of Uranium Dioxide

J. L. Bates

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 26-29

Technical Paper / dx.doi.org/10.13182/NSE65-A21011

The Electrical Conductivity of Alumina at Temperatures in a Reactor Environment

Gary J. Dau, Monte V. Davis

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 30-33

Technical Paper / dx.doi.org/10.13182/NSE65-A21012

Lamellar Compounds of Graphite with Nitrogen Pentoxide as Possible Reactor Hazards

Gerhart Hemig

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 34-39

Technical Paper / dx.doi.org/10.13182/NSE65-A21013

A Graphical Design of an Optimum Control System to Minimize Boiling Reactor Noise

L. Rolf Peterson, Lynn E. Weaver

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 40-48

Technical Paper / dx.doi.org/10.13182/NSE65-A21014

Solving the Transport Equation in Heterogeneous Media Using First-Flight Green's Functions for Homogeneous Media

John P. Church

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 49-61

Technical Paper / dx.doi.org/10.13182/NSE65-A21015

Transport Effects in Diffusion Theory

G. C. Pomraning

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 62-78

Technical Paper / dx.doi.org/10.13182/NSE65-A21016

Heat Transfer to Liquid Metals Flowing Turbulently Between Parallel Plates

O. E. Dwyer

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 79-89

Technical Paper / dx.doi.org/10.13182/NSE65-A21017

Bilateral Heat Transfer to Liquid Metals Flowing Turbulently Through Annuli

O. E. Dwyer, P. S. Tu

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 90-105

Technical Paper / dx.doi.org/10.13182/NSE65-A21018

Thermal Neutron Spectra Near Absorbers

C. B. Bigham

Nuclear Science and Engineering / Volume 21 / Number 1 / January 1965 / Pages 106-113

Technical Paper / dx.doi.org/10.13182/NSE65-A21019

Number 2

Table of Contents
The Thermal Capture Cross Section and Resonance Integral of Uranium-232(J. Halperin, C. R. Baldock and J. H. Oliver)
Criticism of “A Note on the Measurement of the Transport Mean Free Path of Thermal Neutrons in Graphite by a Poison Method”(J. A. DeJuren)
Reply to Remarks by J. A. DeJuren on “A Note on the Measurement of the Transport Mean Free Path of Thermal Neutrons in Graphite by a Poison Method”(G. A. Price)
A Monte Carlo Technique for Selecting Neutron Scattering Angles from Anisotropic Distributions(R. R. Coveyou)
Some Tests of Coveyou's Anisotropic Selection Technique(W. E. Kinney)
The Albedo Problem(G. C. Pomraning)
Neutron Scattering by Polyethylene(Juan U. Koppel and James A. Young)
Void Streaming in SN Calculations(Tom Olsen)
Comments on “Generalizations of Fick's Law”(A. W. Solbrig, Jr.)
Inelastic Scattering of Neutrons in Solids and Liquids(Noel Corngold)
Introduction to Neutron Distribution Theory(R. K. Osborn)
Advances in Computers, Volume 4(Ward Sangren)
Theory and Method of Nuclear Reactor Calculations(John E. Suich)
Nuclear Power Plants: Design, Operating Experience and Economics(Gilbert Melese)
Nuclear Radiation Detection(Frank B. Hall)
Techniques for the Use of Radioisotopes in Analysis(Ralph L. Ely, Jr., Donald L. Wright)

Techniques for In-Pile Measurements of Fission-Gas Release

R. M. Carroll and P. E. Reagan

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 141-146

Technical Paper / dx.doi.org/10.13182/NSE65-A21037

In-Pile Fission-Gas Release from Single-Crystal UO₂

R. M. Carroll and O. Sisman

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 147-158

Technical Paper / dx.doi.org/10.13182/NSE65-A21038

Reactions of Reactor -Irradiated Uranium Monocar bide with Water and with Aqueous Solutions of NaOH, HCl, and H₂SO₄

Mildred J. Bradley, Jerry H. Goode, Leslie M. Ferris, James R. Flanary and Jacob W. Ullmann

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 159-164

Technical Paper / dx.doi.org/10.13182/NSE65-A21039

Plutonium-Fueled Thermal Reactors with High Conversion Ratios

G. Srikantiah and J. Chemick

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 165-178

Technical Paper / dx.doi.org/10.13182/NSE65-A21040

Capture-to-Fission Ratios of U²³³, U²³⁵, U²³⁸ and Pu²³⁹ in EBR-I, Mark III

Carl E. Crouthamel, Donald C. Stupegia, Peter Kafalas and Charles M. Stevens

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 179-185

Technical Paper / dx.doi.org/10.13182/NSE65-A21041

Determination of Excess Reactivity and Control-Rod Worth

T. Auerbach, T. Gozani and P. Schmid

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 186-193

Technical Paper / dx.doi.org/10.13182/NSE65-A21042

Backscattering of Gamma Rays from Point Sources by an Infinite-Plane Concrete Surface

A. B. Chilton

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 194-200

Technical Paper / dx.doi.org/10.13182/NSE65-A21043

Measurement of the Infinite Multiplication Factor in a Natural Uranium, Light-Water Lattice

T. W. T. Burnett and T. G. Williamson

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 201-205

Technical Paper / dx.doi.org/10.13182/NSE65-A21044

The Slowing Down of Neutrons in Hydrogeneous Mixtures

Harvey Amster

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 206-216

Technical Paper / dx.doi.org/10.13182/NSE65-A21045

Criticality of Slightly Enriched Uranium in Water-Moderated Lattices

C. R. Richey, R. C. Lloyd and E. D. Clayton

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 217-226

Technical Paper / dx.doi.org/10.13182/NSE65-A21046

On the Feasibility of Measuring Higher Time Decay Constants

Ajoy K. Ghatak and Henry C. Honeck

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 227-239

Technical Paper / dx.doi.org/10.13182/NSE65-A21047

Boundary Conditions for the Unsymmetrical Spherical-Harmonics Method in Cylindrical Geometry

L. D. Noble and J. O. Mingle

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 240-249

Technical Paper / dx.doi.org/10.13182/NSE65-A21048

Effective Surface of a Tubular Absorber in the Calculation of Resonance Integrals

H. Aisu

Nuclear Science and Engineering / Volume 21 / Number 2 / February 1965 / Pages 250-256

Technical Paper / dx.doi.org/10.13182/NSE65-A21049

Number 3

Table of Contents
Use of Soluble Poisons in Fuel Processing(W. B. Lewis)
Thermal Power of Promethium-147(J. C. Posey, R. S. Pressly, J. H. Gillette)
The Infinite Dilution Resonance Integral of Thorium-232(W. K. Foell, T. J. Connolly)
Statistical-Error Estimation for the Transfer-Function Measurements of a Noisy Reactor System(C. Hsu, W. C. Lipinski)
The Natural Radiation Environment(John W. Winchester)
Materials and Fuels for High-Temperature Nuclear Energy Applications(J. A. McGurty)
CUNLAP(William R. Mills, Jr., L. S. Allen)

A Study of Beryllium-Oxide-Moderated Subcritical Assemblies Containing Various Metal Absorbers

John R. Morton III, James M. Piowaty, Joseph Petruzzi, Loren Gardner

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 289-295

Technical Paper / dx.doi.org/10.13182/NSE65-A20031

Slowing-Down Spectra in ZEEP, ZED-2 and PTR

C. B. Bigham, R. E. Green, A. Okazaki

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 296-303

Technical Paper / dx.doi.org/10.13182/NSE65-A20032

Neutron Slowing-Down Times and Chemical Binding in Water

Ajoy K. Ghatak, Theodore J. Krieger

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 304-311

Technical Paper / dx.doi.org/10.13182/NSE65-A20033

Neutron-Exposure Correlation for Radiation-Damage Studies

R. E. Dahl, H. H. Yoshikawa

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 312-318

Technical Paper / dx.doi.org/10.13182/NSE65-A20034

Effect of Eddy Diffusion on Temperatures in a Fixed-Bed, Particulate-Fueled Nuclear Reactor

James J. Barker, Robert F. Benenati

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 319-324

Technical Paper / dx.doi.org/10.13182/NSE65-A20035

Measurement of the Half-Life of U²³⁵for Alpha Emission

A. J. Deruytter, I. G. Schröder, J. A. Moore

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 325-328

Technical Paper / dx.doi.org/10.13182/NSE65-A20036

Measurement of Asymptotic Neutron Spectra in Multiplying Assemblies Containing U²³⁵

R. E. Slovacek, E. R. Gaerttner, R. R. Fullwood, D. R. Bach

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 329-345

Technical Paper / dx.doi.org/10.13182/NSE65-A20037

Pulsed-Neutron Experiments in a Borehole Model

William R. Mills, Jr., L. Scott Allen, Richard L. Caldwell, George N. Salaita, Tom J. Gray

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 346-356

Technical Paper / dx.doi.org/10.13182/NSE65-A20038

Reactor Neutron-Pulse Propagation

George H. Miley

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 357-368

Technical Paper / dx.doi.org/10.13182/NSE65-A20039

Neutron Fluctuations in a Reactor of Finite Size

D. R. Harris

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 369-381

Technical Paper / dx.doi.org/10.13182/NSE65-A20040

A Transport Theoretic Calculation of the Disadvantage Factor

Joel H. Ferziger, Alan H. Robinson

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 382-389

Technical Paper / dx.doi.org/10.13182/NSE65-A20041

On the Stochastic Theory of Neutron Transport

George I. Bell

Nuclear Science and Engineering / Volume 21 / Number 3 / March 1965 / Pages 390-401

Technical Paper / dx.doi.org/10.13182/NSE65-1

Number 4

Table of Contents
Wear Rates in Automotive Engines by Liquid Scintillation Counting of Fe⁵⁵(H. H. Ross, R. P. Gardner, J. W. Dunn)
Comments on the Existence of Exceptional Frequencies in Multiplying Media(R. L. Brehm)
Multilevel Cross Sections and Reactor Criticality(M. Goldsmith, N. R. Candelore)
A Semi-Empirical Description of the Detailed Thermal Flux Distribution in Uranium Oxide Clusters(P. F. Palmedo)
A Phase Integral Study of Neutron Thermalization in Graphite(Ajoy K. Ghatak)
The Atomic Adventure(Lewis L. Strauss)
Nuclear and Radiochemistry(Don M. Yost)
Neutron Physics(Jack Chernick)
Fundamentals of Heat Transfer(C. F. Bonilla)
Inorganic Ion Exchangers(Lawrence Dresner)
Effects of Radiation on Materials and Components(C. G. Collins)
CCA - 94(Charles W. Friend, J. R. Knight)
CCA - 96(Charles W. Friend, R. B. Smith, J. Spanier, A. E. Sumner, Jr.)
CCA - 97(N. R. Candelore, R. C. Gast)
CCA - 98(John H. Bennett)

The Advanced Epithermal Thorium Reactor (AETR) Critical Experiments

L. A. Mountford and H. A. Morewitz

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 421-428

Technical Paper / dx.doi.org/10.13182/NSE65-A18786

Reactivity Measurements in the Advanced Epithermal Thorium Reactor (AETR) Critical Experiments

S. G. Carpenter

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 429-440

Technical Paper / dx.doi.org/10.13182/NSE65-A18787

Fission-Rate Measurements in the Advanced Epithermal Thorium Reactor (AETR) Critical Experiments

Donald Strominger and Gordon Schlesinger

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 441-450

Technical Paper / dx.doi.org/10.13182/NSE65-A18788

Neutron-Importance Measurements in the Advanced Epithermal Thorium Reactor (AETR) Critical Experiments

Robert J. Tuttle

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 451-462

Technical Paper / dx.doi.org/10.13182/NSE65-A18789

Hydraulic Instability of Flat Parallel-Plate Assemblies

R. J. Scavuzzo

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 463-472

Technical Paper / dx.doi.org/10.13182/NSE65-A18790

A Method of Predicting Steam-Surge Tank Transients Based on One-Dimensional Heat Sinks

Eugene E. Drucker and Dannie J. Gorman

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 473-480

Technical Paper / dx.doi.org/10.13182/NSE65-A18791

The Variation of k_∞ with Fuel Temperature for a Uranium Fuel Element

R. I. Smith

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 481-489

Technical Paper / dx.doi.org/10.13182/NSE65-A18792

Burnout and Heat-Transfer Correlations for Once-Through Superheat at Low Flow with an Exponential Source

E. E. Duke

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 490-497

Technical Paper / dx.doi.org/10.13182/NSE65-A18793

Anisotropic Scattering Approximations in the Monoenergetic Boltzmann Equation

K. D. Lathrop

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 498-508

Technical Paper / dx.doi.org/10.13182/NSE65-A18794

Beam-Port Perturbations in Water and Graphite

Sanford C. Cohen and John S. King

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 509-514

Technical Paper / dx.doi.org/10.13182/NSE65-A18795

Measurement of the Angular Distribution of Thermal Neutrons at the Surfaces of Cadmium Rods

D. E. Wood

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 515-522

Technical Paper / dx.doi.org/10.13182/NSE65-A18796

Doppler Effect Calculations with Interference Corrections

R. N. Hwang

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 523-535

Technical Paper / dx.doi.org/10.13182/NSE65-A18797

Space-Dependent Effects in the Response of a Nuclear Reactor to Forced Oscillations

William E. Loewe

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 536-549

Technical Paper / dx.doi.org/10.13182/NSE65-A18798

Nonlinear Reactor Kinetics Analysis

H. L. Garabedian and R. E. Lynch

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 550-564

Technical Paper / dx.doi.org/10.13182/NSE65-A18799

The Determination of Reactor Dispersion Laws from Modulated-Neutron Experiments

M. N. Moore

Nuclear Science and Engineering / Volume 21 / Number 4 / April 1965 / Pages 565-574

Technical Paper / dx.doi.org/10.13182/NSE65-A18800