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Volume 51

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Number 1

Table of Contents
Dynamics of Nuclear Systems(Noel Corngold)
Application of Invariant Imbedding to Reactor Physics(Zbigniew Weiss)
Radioisotope Engineering(Joseph Silverman)
Comments on “Merit Index for Gas-Cooled Reactor Heat Transfer”(D. C. Leslie)
Reply to “Comments on ‘Merit Index for Gas-Cooled Reactor Heat Transfer’ ”(G. Melese-d’Hospital)
Theoretical Dose Transmission and Reflection Probabilities for 0.2 - 10.0 MeV Photons Obliquely Incident on Finite Concrete Barriers(W. O. Doggett, Fred A. Bryan, Jr.,)
Variational Estimates of Reactivity Worths and Reaction Rate Ratios in Critical Nuclear Reactors(Weston M. Stace, Jr.,)

Fast Reactor Design Optimization System with a Method of Nonlinear Programming

Kotaro Inoue

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE73-A23252

On the Control of Spatial Xenon Oscillations

A. M. Christie, C. G. Poncelet

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 10-24

Technical Paper / dx.doi.org/10.13182/NSE73-A23253

Measurement and Evaluation of Total Neutron Cross-Section Minima in Elemental Iron from 24 to 750 keV

K. A. Alfieri, R. C. Block, P. J. Turinsky

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 25-31

Technical Paper / dx.doi.org/10.13182/NSE73-A23254

Low Energy Components of Scattered Gamma Radiation

Susumu Minato

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 32-40

Technical Paper / dx.doi.org/10.13182/NSE73-A23255

Evaluation of Lumped Parameter Heat Transfer Techniques for Nuclear Reactor Applications

D. M. France, T. Ginsberg

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 41-51

Technical Paper / dx.doi.org/10.13182/NSE73-A23256

The Energy Distribution of Delayed Fission Neutrons

S. Shalev, J. M. Cuttler

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 52-66

Technical Paper / dx.doi.org/10.13182/NSE73-A23257

A New Method of Solving the Multimode Reactor Kinetics Equations

J. C. Turnage

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 67-76

Technical Note / dx.doi.org/10.13182/NSE73-A23258

On a Multidirectional Modal Representation for Neutron Transport Analysis

A. A. Harms, S. A. Kushneriuk

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 76-78

Technical Note / dx.doi.org/10.13182/NSE73-A23259

An Exact Analytical Solution of an Elementary Critical Condition

C. E. Siewert

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Page 78

Technical Note / dx.doi.org/10.13182/NSE73-A23260

A Simple Analytic Transient Flux Expression for Use With Asymptotic Diffusion Theory

L. E. Beghian, I. A. Forbes, V. C. Rogers

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 78-83

Technical Note / dx.doi.org/10.13182/NSE73-A23261

Absolute Neutron Yields from Alpha-Particle Interaction with Thick Targets of Natural Carbon

J. K. Bair

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 83-84

Technical Note / dx.doi.org/10.13182/NSE73-A23262

Heat Conduction in the UO₂-Cladding Composite Body with Simultaneous Solidification and Melting

Michael Epstein

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 84-87

Technical Note / dx.doi.org/10.13182/NSE73-A23263

Number 2

Table of Contents
On Semigroup Theory and Its Application to Space-Time Nucleary Reactor Dynamics(Raymond M. Crawford, William E. Kastenberg)
An Analysis of the Doppler Effect of Structural Materials(Yukio Ishiguro)

On the Mechanism of Uranium Dioxide-Sodium Explosive Interactions

Hans K. Fauske

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 95-101

Technical Paper / dx.doi.org/10.13182/NSE73-A26584

Gamma-Ray Attenuation in Basement Ceilings

R. S. Reynolds

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 102-112

Technical Paper / dx.doi.org/10.13182/NSE73-A26585

Gamma-Ray Spectra from the Interaction of 14-MeV Neutrons with Copper, Zirconium, and Antimony

Michael Stamatelatos, Bo Lawergren, Leon J. Lidofsky

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 113-118

Technical Paper / dx.doi.org/10.13182/NSE73-A26586

Resonances Suitable for the Calibration of a Time-of-Flight Neutron Spectrometer

S. Wynchank, F. Rahn, H. S. Carmada, G. Hacken, M. Slagowitz, H. I. Liou, J. Rainwater, W. W. Havens, Jr.

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 119-123

Technical Paper / dx.doi.org/10.13182/NSE73-A26587

A Measurement of the Fission Cross Section of Plutonium-241 Relative to Uranium-235

F. Käppeler, E. Pfletschinger

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 124-129

Technical Paper / dx.doi.org/10.13182/NSE73-A26588

High Resolution Measurements of Neutron-Induced Fission Cross Sections for ²³³U, ²³⁵U, ²³⁹Pu and ²⁴¹Pu Below 30 keV

J. Blons

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 130-147

Technical Paper / dx.doi.org/10.13182/NSE73-A26589

The Application of Phase-Space Finite Elements to the One-Dimensional Neutron Transport Equation

W. F. Miller, Jr., E. E. Lewis, E. C. Rossow

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 148-156

Technical Paper / dx.doi.org/10.13182/NSE73-A26590

One-Speed Neutron Transport Problems-Part I: Exact Transfer Matrix Formulation

Raphael Aronson

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 157-165

Technical Paper / dx.doi.org/10.13182/NSE73-A26591

One-Speed Neutron Transport Problems-Part II: Slab Transmission and Reflection and Finite Reflector Critical Problems

Gerhard Caroll and Raphael Aronson

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 166-179

Technical Paper / dx.doi.org/10.13182/NSE73-A26592

Higher Order Perturbation Method in Reactor Calculations

Hiroshi Mitani

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 180-188

Technical Paper / dx.doi.org/10.13182/NSE51-180

Solution of the Space-Dependent Reactor Kinetics Equations in Three Dimensions

D. R. Ferguson, K. F. Hansen

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 189-205

Technical Paper / dx.doi.org/10.13182/NSE73-A26594

On Autocatalysis During Fast Reactor Disassembly

Jay E. Boudreau, R. C. Erdmann

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 206-222

Technical Paper / dx.doi.org/10.13182/NSE73-A26595

Experimental Fast-Neutron Albedo from Plane Scatterers

Y. Segal, U. German, A. Notea

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 223-234

Technical Note / dx.doi.org/10.13182/NSE73-A26596

Measurement of the Neutron Total Cross Sections of Zircaloy-2, Zirconium-90, and Carbon between 0.4 and 2.4 MeV

R. W. Stooksberry, J. H. Anderson

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 235-238

Technical Note / dx.doi.org/10.13182/NSE73-A26597

The Sensitivity of Neutron Transport Calculations to Nonelastic Neutron Angular Distributions

Ernest F. Plechaty

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 239-242

Technical Note / dx.doi.org/10.13182/NSE73-A26598

Evaluation of the Second-Order Perturbation Terms by the Generalized Perturbation Method

Yasushi Seki

Nuclear Science and Engineering / Volume 51 / Number 2 / June 1973 / Pages 243-251

Technical Note / dx.doi.org/10.13182/NSE51-243

Number 3

Table of Contents
Introduction to Atomic and Nuclear Physics(J. H. Hamilton)

Space-Dependent Neutron Noise Spectra in Bare and D₂O-Reflected Reactor Lattices

C. O. Thomas, Jr., S. H. Hanauer, N. P. Baumann

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 253-261

Technical Paper / dx.doi.org/10.13182/NSE73-A26603

Measurements of Spatially Independent Reactivity in Pulsed-Neutron Experiments

F. C. Difilippo, N. B. Pieroni, J. C. Viez

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 262-271

Technical Paper / dx.doi.org/10.13182/NSE73-A26604

Multiple Reaction Correction to Neutron Reaction Cross Sections

Joseph J. Devaney

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 272-277

Technical Paper / dx.doi.org/10.13182/NSE73-A26605

Measurements and Calculations of the Neutron Spectra from Iron Bombarded with 14-MeV Neutrons

L. F. Hansen, J. D. Anderson, P. S. Brown, R. J. Howerton, J. L. Kammerdiener, C. M. Logan, E. F. Plechaty, C. Wong

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 278-295

Technical Paper / dx.doi.org/10.13182/NSE73-A26606

Gamma-Ray Production Cross Sections of Neutron-Induced Uranium-238 Reactions

Hiroshi Takahashi

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 296-315

Technical Paper / dx.doi.org/10.13182/NSE73-A26607

Optimum Eigenvalue Bounds for Neutron Diffusion and Transport Theory

David B. Reister

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 316-323

Technical Paper / dx.doi.org/10.13182/NSE73-A26608

Inner Iteration Error in the S_N Algorithm

Gerald L. Atkinson, William Kerr, James J. Duderstadt

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 324-330

Technical Paper / dx.doi.org/10.13182/NSE73-A26609

Multigroup Diffusion Coefficients from Transport Theory

O. J. Sheaks, L. Harold Sullivan, Raymond L. Murray

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 331-335

Technical Note / dx.doi.org/10.13182/NSE73-A26610

Effect of Shape of the Assembly on the Decay Constant in Pulsed-Neutron Experiments

Feroz Ahmed, Rajesh Mohan

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 335-337

Technical Note / dx.doi.org/10.13182/NSE73-A26611

Total Gamma-Ray Cross Sections

M. V. Ramana Murty, K. Parthasaradhi, S. Ramamurty

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 337-339

Technical Note / dx.doi.org/10.13182/NSE73-A26612

A Class of Second-Order Approximate Formulations of Deep Penetration Radiation Transport Problems

S. A. W. Gerstl, W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 51 / Number 3 / July 1973 / Pages 339-343

Technical Note / dx.doi.org/10.13182/NSE73-A26613

Number 4

Table of Contents
Transport Results for the Uniform Source Half-Space Problem(G. C. Pomraning)
Reply to “Transport Results for the Uniform Source Half-Space Problem”(W. P. Petrick, C. T. McDaniel, A. Leonard)

The Stability of Power Reactors Subject to Stochastic Macroscopic Parameter Variation

G. A. Krist, C. G. Poncelet

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 347-375

Technical Paper / dx.doi.org/10.13182/NSE73-A23272

Fission Cross Section of Californium-249

M. G. Silbert

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 376-384

Technical Paper / dx.doi.org/10.13182/NSE73-A23273

Measurement of the Uranium-238 Capture Cross Section for Incident Neutron Energies up to 100 keV

G. de Saussure, E. G. Silver, R. B. Perez, R. Ingle, H. Weaver

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 385-404

Technical Paper / dx.doi.org/10.13182/NSE73-1

Thermal-Neutron Spectrum Indexes in D₂O-Moderated Uranium and Uranium-Plutonium Fuel Elements in the Temperature Range from 20 to 200°C

S. Guardini, N. Schiavone, S. Tassan

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 405-414

Technical Paper / dx.doi.org/10.13182/NSE73-A23275

Heterogeneity Effects in ZPPR Assembly 2—A Plutonium-Fueled Demonstration Fast Reactor Study

W. G. Davey, P. I. Amundson, P. J. Collins, R. G. Palmer

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 415-440

Technical Paper / dx.doi.org/10.13182/NSE73-A23276

Neutron Resonance Absorption in Heterogeneous Fast Reactor Assemblies

Yukio Ishiguro

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 441-455

Technical Paper / dx.doi.org/10.13182/NSE73-A23277

Finite Element Methods for Reactor Analysis

C. M. Kang, K. F. Hansen

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 456-495

Technical Paper / dx.doi.org/10.13182/NSE73-A23278

Neutron Capture Gamma-Ray Yields in Iron

J. E. White, C. Y. Fu, K. J. Yost

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 496-508

Technical Note / dx.doi.org/10.13182/NSE73-A23279

Elastic Scattering Probability Functions in Arbitrary Coordinate Systems

B. R. Wienke

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 508-511

Technical Note / dx.doi.org/10.13182/NSE73-A23280

Application of Intermediate Treatment of Resonance Absorption to Heterogeneous Fast Reactor Assembly

Yukio Ishiguro

Nuclear Science and Engineering / Volume 51 / Number 4 / August 1973 / Pages 512-514

Technical Note / dx.doi.org/10.13182/NSE73-A23281