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Volume 44

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Number 1

Table of Contents
BRT-1: Battelle Revised Thermos(C. L. Bennett, W. L. Purcell)
DBLSCAT: A Computer Code for Double Scattering Corrections(Ashok K. Agrawal, Shashi G. Das)
Comments on Residual Power Fluxes from Radioactive Surfaces(Robert A. Schlenker)
Reply to Comments on Residual Power Fluxes from Radioactive Surfaces(Jacob B. Romero)
Comments on Certain Instabilities in the “Initial Value” Problem(V. Protopopescu)
Pressure Distribution for Axisymmetric Two-Dimensional Flow in a Plenum During Coolant Explusion(T. C. Chawla, B. M. Hoglund)
Elementary Radiation Physics(Hugh F. Henry)

A Physical Basis for Two-Phase Pressure Gradient and Critical Flow Calculations

P. E. Tremblay, D. G. Andrews

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE71-A18899

Influence of Coated-Particle Structure in Thermal-Neutron-Spectrum Energy Range

U. Hansen, E. Teuchert

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 12-17

Technical Paper / dx.doi.org/10.13182/NSE44-12

An Analysis of Bare and Reflected Metal Critical Assemblies Using ENDF/B Data

Hans Ludewig

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 18-26

Technical Paper / dx.doi.org/10.13182/NSE71-A18901

Solutions of the Diffusion Equation by the Spectral-Synthesis Method

Paul G. Lorenzini, Alan H. Robinson

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 27-36

Technical Paper / dx.doi.org/10.13182/NSE71-A18902

A Simplified, Coarse-Mesh, Three-Dimensional Diffusion Scheme for Calculating the Gross Power Distribution in a Boiling Water Reactor

S. Børresen

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 37-43

Technical Paper / dx.doi.org/10.13182/NSE71-A18903

An Altered Diffusion Theory Based on the Double P-0 Approximation for All Geometries

Stefano L. Paveri-Fontana, Harvey Amster

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 44-57

Technical Paper / dx.doi.org/10.13182/NSE71-A18904

The Tensor Form of the Neutron-Transport Equation with Application to Finite Differencing

D. W. Drawbaugh

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 58-65

Technical Paper / dx.doi.org/10.13182/NSE71-A18905

Reactor Kinetic Parameters of Lattices of Plutonium and Uranium in Water

V. O. Uotinen, J. H. Lauby, W. P. Stinson, S. R. Dwivedi

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 66-71

Technical Paper / dx.doi.org/10.13182/NSE71-A18906

Improved Spatial Differencing for the Solution of Space-Time Problems Arising from the Movement of Reactor Materials

J. B. Yasinsky, L. R. Foulke

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 72-85

Technical Paper / dx.doi.org/10.13182/NSE71-A18907

On the Determination of Stability Domains in Nonlinear Point Reactor Dynamics

Richard Ziskind, William E. Kastenberg

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 86-94

Technical Paper / dx.doi.org/10.13182/NSE71-A18908

Tests of Evaluated Beryllium (n, 2n) Cross Sections by Analysis of 1.4-eV Flux in Water for an Americium-Beryllium Source Enclosed in Beryllium Spheres

Roger L. Alexander, Daniel Fieno, C. Hubbard Ford

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 95-102

Technical Note / dx.doi.org/10.13182/NSE71-A18909

Pair-Production Cross Sections at 2.75 MeV

H. F. Atwater

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 102-104

Technical Note / dx.doi.org/10.13182/NSE71-A18910

An Approximate High-Energy Alpha-Particle Nucleus Collision Model

T. A. Gabriel, R. T. Santoro, R. G. Alsmiller, Jr.

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 104-110

Technical Note / dx.doi.org/10.13182/NSE71-A18911

Subcritical Reactivity from Reactor Noise

Andreas Szeless, Lawrence Ruby

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Pages 110-112

Technical Note / dx.doi.org/10.13182/NSE71-A18912

Comment on Subcritical Reactivity from Reactor Noise

Robert W. Albrecht

Nuclear Science and Engineering / Volume 44 / Number 1 / April 1971 / Page 112

Technical Note / dx.doi.org/10.13182/NSE71-A18913

Number 2

Table of Contents
Continuous Slowing Down Theory Applied to Fast Reactor Assemblies(W.M.Stacey, Jr.)
General-Geometry TWOTRAN(K. D. Lathrop)

Maximizing the Average Fuel Burnup Over Entire Core: A Poison Management Optimization Problem for Multizone Light-Water Reactor Cores

Atsuyuki Suzuki, Ryohei Kiyose

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 121-134

Technical Paper / dx.doi.org/10.13182/NSE71-A19662

An Integrated Model for Analyzing Disruptive Accidents in Fast Reactors

William T. Sha, Alan E. Waltar

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 135-156

Technical Paper / dx.doi.org/10.13182/NSE71-A19663

Calculations of Weapon Radiation Doses in Single-Compartment Aboveground Concrete Structures

L. G. Mooney

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 157-172

Technical Paper / dx.doi.org/10.13182/NSE71-A19664

Measurement of the Delayed-Neutron Fractions for Thermal Fission of Uranium-235, Plutonium-239, and Uranium-233

John F. Conant, Philip F. Palmedo

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 173-179

Technical Paper / dx.doi.org/10.13182/NSE71-A19665

Epithermal Measurements of Capture and Fission Resonance Integrals in ²³⁵U, ²³³U, ²³⁹Pu, and ²⁴¹Pu

H. M. Eiland, L. J. Esch, F. Feiner, J. L. Mewherter

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 180-189

Technical Paper / dx.doi.org/10.13182/NSE71-A19666

Neutron Yield from the (α, n) Reaction in the Isotope Oxygen-18

Mojtaba Taherzadeh

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 190-193

Technical Paper / dx.doi.org/10.13182/NSE71-A19667

The Effect of Anisotropic Scattering Upon the Elastic Moderation of Fast Neutrons

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 194-203

Technical Paper / dx.doi.org/10.13182/NSE71-A19668

Synthesis of Fast Reactor Space-Energy Neutron Fluxes

P. A. Ombrellaro

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 204-220

Technical Paper / dx.doi.org/10.13182/NSE71-A19669

Measurements and Calculations of Neutron Migration and its Anisotropy in Lattices of Fuel Rods and Liquid Coolant

D. R. Harris, J. A. Mitchell

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 221-238

Technical Paper / dx.doi.org/10.13182/NSE71-A19670

Application of Alternating-Direction Implicit Methods to the Space-Dependent Kinetics Equations

A. L. Wight, K. F. Hansen, D. R. Ferguson

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 239-251

Technical Paper / dx.doi.org/10.13182/NSE71-A19671

Neutron Streaming Through Ducts—Analysis of Experimental Results

Y. T. Song, C. M. Huddleston, A. B. Chilton

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 252-261

Technical Note / dx.doi.org/10.13182/NSE71-A19672

An Improved Method for Calculating Foil Perturbation Effects

Darrell F. Newman

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 261-266

Technical Note / dx.doi.org/10.13182/NSE71-A19673

Values of Eta of Uranium-233, Uranium-235, and Plutonium-239 from Critical Experiments and Reactivity Measurements

D. W. Magnuson

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 266-267

Technical Note / dx.doi.org/10.13182/NSE71-A19674

Optimization of Nuclear Systems by Geometric Programming

G. D. Bouchey, C. S. Beightler, B. V. Koen

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 267-272

Technical Note / dx.doi.org/10.13182/NSE71-A19675

Some Comments on Perturbation Theory

D. S. Selengut

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 272-275

Technical Note / dx.doi.org/10.13182/NSE71-A19676

Number 3

Table of Contents
Comments on An Improved Collision Probability Method for Thermal-Neutron-Flux Calculation in a Cylindrical Reactor Cell(J. D. Stewart)
Reply to the Comments of J. D. Stewart on the Calculation of Thermal-Neutron Flux(Tome Boševski)
Collision Probabilities for Finite Cylinders and Cuboids(I. Carlvik)
The Calculation of Gamma-Ray Transition Probabilities in Odd-A Nuclei(K. J. Yost, P. H. Pitkanen, C. Y. Fu)

An Analytical and Experimental Investigation of the Vibration of Cylindrical Reactor Fuel Elements in Two-Phase Parallel Flow

D. J. Gorman

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 277-290

Technical Paper / dx.doi.org/10.13182/NSE71-A20161

A Generalized Local Boiling Void Model for Light-Water Reactor System

William T. Sha

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 291-300

Technical Paper / dx.doi.org/10.13182/NSE71-A20162

Dynamic Stability of Cylindrical Shells Subjected to Sonic Waves Due to a Loss-of-Coolant Reactor Accident

George J. Bohm, Elmar A. Steck

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 301-309

Technical Paper / dx.doi.org/10.13182/NSE71-A20163

Carbon Loss from Graphite Cylinders Exposed to Steam for Short Times

M. Necati Özişik, H. J. de Nordwall

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 310-319

Technical Paper / dx.doi.org/10.13182/NSE71-A20164

A Study of Coolant Transients During a Rapid Fission Gas Release in a Fast Reactor Subassembly

T. C. Chawla, B. M. Hoglund

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 320-344

Technical Paper / dx.doi.org/10.13182/NSE71-A20165

An Evaluation of the Number of Neutrons Per Fission for the Principal Plutonium, Uranium, and Thorium Isotopes

W. G. Davey

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 345-371

Technical Paper / dx.doi.org/10.13182/NSE71-A20166

Effect of Moderation on Reaction Cross-Section Measurements

Melvin M. Levine

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 372-375

Technical Paper / dx.doi.org/10.13182/NSE71-A20167

Fast Neutron Penetration in Paraffin and Lithium Hydride

A. E. Profio, R. J. Cerbone, D. L. Huffman

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 376-387

Technical Paper / dx.doi.org/10.13182/NSE71-A20168

The Measurement of Flux Fine Structure in Plate Fast Reactor Cells of Finite Size

Philip F. Palmedo, Henry H. Windsor

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 388-397

Technical Paper / dx.doi.org/10.13182/NSE71-A20169

An Analysis of Flux Fine Structure in One-Dimensional Fast Reactor Cells

Hans Ludewig

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 398-405

Technical Paper / dx.doi.org/10.13182/NSE71-A20170

Bounded Estimators for Flux at a Point in Monte Carlo

Herbert A. Steinberg, Malvin H. Kalos

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 406-412

Technical Paper / dx.doi.org/10.13182/NSE71-A20171

The Reactivity Effect of Replacing a Water Reflector with Lead

G. Klotzkin, R. F. Valentine, C. A. Flanagan, J. C. Stachew

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 413-422

Technical Paper / dx.doi.org/10.13182/NSE71-A20172

The SP_N-P_L Method for Neutron Transport in Homogeneous Slabs with Anisotropic Scattering

H. Kschwendt

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 423-434

Technical Paper / dx.doi.org/10.13182/NSE71-A20173

The Influence of Power Flattening on Hot Channel Factors

A. Amendola

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 435-437

Technical Note / dx.doi.org/10.13182/NSE71-A20174

Thick Target Yields for the ⁹Be(α, n) Reaction

M. E. Anderson, M. R. Hertz

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 437-439

Technical Note / dx.doi.org/10.13182/NSE71-A20175

Note on the Prompt-Fission-Neutron Spectra of Uranium-235 and Plutonium-239

A. B. Smith

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 439-442

Technical Note / dx.doi.org/10.13182/NSE71-A20176

Approximate Treatments of the Effect of Anisotropy on Elastic Neutron Moderation

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 442-444

Technical Note / dx.doi.org/10.13182/NSE71-A20177

Slowing Down and Heating Up of Neutrons in Graphite at Low Temperatures

Vidya Bhushan, S. K. Trikha

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 444-447

Technical Note / dx.doi.org/10.13182/NSE71-A20178

Adjoint Spectra for Calculating Thermal Group Constants

D. S. Selengut

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 447-449

Technical Note / dx.doi.org/10.13182/NSE71-A20179

A Theorem Concerning Reflection and Transmission from a Nonabsorbing Slab

Raphael Aronson

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 449-450

Technical Note / dx.doi.org/10.13182/NSE71-A20180

Experimental Determination of the Perturbation Denominator in Fast Critical Assemblies

W. C. Redman, M. M. Bretscher

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 450-453

Technical Note / dx.doi.org/10.13182/NSE71-A20181