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Volume 49

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Number 1

Table of Contents
ESP: A General Reactor Analysis Monte Carlo Code(S. N. Cramer R. S. Carlsmith G. W. Morrison,LG. W. Perry J. L. Lucius)
HETC: A High Energy Transport Code(T. W. Armstrong, K. C. Chandler)
Comments on Variation Flux Synthesis Methods for Multigroup Diffusion Theory(A. J. Buslik)
Reply to “Comments on Variation Flux Synthesis Methods for Multigroup Diffusion Theory”(W. M. Stacey, Jr.)

Discrete Ordinate Neutron Transport Equation Equivalent to P_L Approximation

Jungchung Jung, Hiroshi Chijiwa, Keisuke Kobayashi,Hiroshi Nishihara

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE49-01-01

Spherical Harmonic Solutions of the Neutron Transport Equation from Discrete Ordinate Codes

Wm. H. Reed

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 10-19

Technical Paper / dx.doi.org/10.13182/NSE72-A22523

Effect of Singularities on Approximation in S_N Methods

Jacek Arkuszewski, Teresa Kulikowska, Janusz Mika

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 20-26

Technical Paper / dx.doi.org/10.13182/NSE72-4

A Timing Comparison Study for Some High Order Finite Element Approximation Procedures and a Low Order Finite Difference Approximation Procedure for the Numerical Solution of the Multigroup Neutron Diffusion Equation

Hans G. Kaper, Gary K. Leaf, Arthur J. Lindeman

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 27-48

Technical Paper / dx.doi.org/10.13182/NSE72-A22525

Spherical Harmonics Treatment of Epithermal Neutron Spectra in Reactor Lattices

M. V. Mataušek

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 49-58

Technical Paper / dx.doi.org/10.13182/NSE72-A22526

In-Core Fuel Management Optimization by Heuristic Learning Technique

Tsutomu Hoshino*

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 59-71

Technical Paper / dx.doi.org/10.13182/NSE72-A22527

The Yield Stress Radiation Damage Function of Iron

G. R. Odette, T. O. Ziebold

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 72-81

Technical Paper / dx.doi.org/10.13182/NSE72-A22528

Monte Carlo Calculations of High-Energy Nucleon-Meson Cascades and Comparison with Experiment

T. W. Armstrong, R. G. Alsmiller, Jr., K. C. Chandler, B. L. Bishop

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 82-92

Technical Paper / dx.doi.org/10.13182/NSE72-A22529

A Numerical Calculation of the Redistribution of an Interstitial Solute in a Thermal Gradient

G. P. Marino

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 93-98

Technical Paper / dx.doi.org/10.13182/NSE72-A22530

Linear Stability of Fast and Thermal Reactor Models Using Space-Time Kinetics

Kenneth Alvin Solomon and William E. Kastenberg

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 99-103

Technical Note / dx.doi.org/10.13182/NSE72-A22531

Experimentally Measured Dose Albedos of Intermediate Energy Bremsstrahlung

Thomas R. Crites

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 103-106

Technical Note / dx.doi.org/10.13182/NSE72-A22532

Hot Spot Expectation in Nuclear Reactor Core Thermal Design

A. Amendola

Nuclear Science and Engineering / Volume 49 / Number 1 / September 1972 / Pages 106-108

Technical Note / dx.doi.org/10.13182/NSE72-A22533

Number 2

Table of Contents
Experimental Neutron Thermalization(H. L. Me Murry)
A First Course in Turbulence(David G. Thomas)
Theoretical Analysis of Homogeneous Plutonium Critical Experiments(C. R. Richey)

Inverse Compton Scattering as an Energy Loss Mechanism in a Controlled Thermonuclear Reactor

Paul A. Robinson, Jr., George D. Sauter

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 117-129

Technical Paper / dx.doi.org/10.13182/NSE72-A35500

Neutron Displacement Cross Sections for Stainless Steel and Tantalum Based on a Lindhard Model

D. G. Doran

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 130-144

Technical Paper / dx.doi.org/10.13182/NSE72-A35501

The Total Neutron Cross Sections of the Curium Isotopes from 0.01 to 30 eV

J. R. Berreth, F. B. Simpson, B. C. Rusche

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 145-152

Technical Paper / dx.doi.org/10.13182/NSE72-A35502

Neutron Capture, Fission, and Total Cross Sections of Plutonium-240 from 20 eV to 30 keV

R. W. Hockenbury, W. R. Moyer, R. C. Block

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 153-161

Technical Paper / dx.doi.org/10.13182/NSE72-A35503

Neutron Angular Distribution Analysis Using Cylindrical Bessel Functions

S. Pearlstein

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 162-171

Technical Paper / dx.doi.org/10.13182/NSE72-A35504

On the Application of Eigenfunction Expansions to Problems in Nonlinear Space-Time Reactor Dynamics

Edmund T. Rumble, III, William E. Kastenberg

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 172-187

Technical Paper / dx.doi.org/10.13182/NSE72-A35505

Local Nuclear Reactor Power Measurements Using Gamma-Ray Fluctuations

F. E. LeVert, M. A. Schultz

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 188-201

Technical Paper / dx.doi.org/10.13182/NSE72-A35506

A Two Overlapping-Group Transport Computational Method for Thermal Neutron Problems

M. Natelson, E. M. Gelbard

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 202-212

Technical Paper / dx.doi.org/10.13182/NSE72-A35507

An Improved Reactivity Table Model for Liquid Metal Fast Breeder Reactor Dynamics

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 213-227

Technical Paper / dx.doi.org/10.13182/NSE72-A35508

An Analysis of the Doppler Effect of Structural Materials

Yukio Ishiguro

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 228-232

Technical Note / dx.doi.org/10.13182/NSE72-A35509

The Neutron Spectrum from a Fission Source in Water

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

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 232-236

Technical Note / dx.doi.org/10.13182/NSE72-A35510

Measurements of the Effective Delayed-Neutron Fraction in Two Fast Critical Experiments

S. G. Carpenter, J. M. Gasidlo, J. M. Stevenson

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 236-239

Technical Note / dx.doi.org/10.13182/NSE72-2

A Simple Computational Model for Rod Motion Transients

D. J. Diamond, G. S. Lellouche, M. M. Levine

Nuclear Science and Engineering / Volume 49 / Number 2 / October 1972 / Pages 239-243

Technical Note / dx.doi.org/10.13182/NSE72-A35512

Number 3

Tritium Generation in the Coolant-Moderator of Pressurized Water Reactors

Karl Hornyik

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 247-254

Technical Paper / dx.doi.org/10.13182/NSE72-A22539

Optimum Binary Signals for Reactor Frequency Response Measurements

M. R. Buckner, T. W. Kerlin

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 255-262

Technical Paper / dx.doi.org/10.13182/NSE72-A22540

Minimum Critical Mass in Intermediate Reactors Subject to Constraints on Power Density and Fuel Enrichment

P. Goldschmidt

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 263-273

Technical Paper / dx.doi.org/10.13182/NSE72-A22541

Critical Experiments for the Brookhaven Pulsed Fast Reactor Study

J. Phelps, H. Windsor, H. Takahashi, J. Conant, K. Chandramoleswar

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 274-300

Technical Paper / dx.doi.org/10.13182/NSE72-A22542

The Angular Distribution of Thermal Neutrons at the Surfaces of Black and Grey Cylinders

D. G. Doutriaux, D. G. Andrews

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 301-309

Technical Paper / dx.doi.org/10.13182/NSE72-A22543

The Ratio of the Uranium-238 to Uranium-235 Fission Cross Sections from 1 to 5 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 310-316

Technical Paper / dx.doi.org/10.13182/NSE72-A22544

Neutron Capture Cross Sections in the keV Region for 154Sm, ¹⁶⁰Gd, ¹⁶⁴Dy, and ¹⁶⁵Ho

L. R. Fawcett, Jr., A. Keith Furr, J. G. Lindsay

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 317-329

Technical Paper / dx.doi.org/10.13182/NSE72-A22545

Measurement and Analysis of Fast Neutron Spectra in Uranium Depleted in the Uranium-235 Isotope

N. N. Kaushal, B. K. Malaviya, M. Becker, E.T. Burns, E. R. Gaerttner

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 330-348

Technical Paper / dx.doi.org/10.13182/NSE72-A22546

Evaluation of Gamma-Ray Shielding Calculations and Determination of Shielding Parameters with Bremsstrahlung Radiation

L. F. Rodriguez, A. Shapiro

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 349-357

Technical Paper / dx.doi.org/10.13182/NSE72-A22547

Measurement of the Ratio of the Prompt to the Delayed Neutronic Response of a Self-Powered Vanadium Detector by Cross-Correlation Techniques

W. Seifritz

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 358-369

Technical Paper / dx.doi.org/10.13182/NSE72-A22548

The Integral Transform Method for the Average Neutron Transport Properties of a Lattice

M. opi

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 370-376

Technical Note / dx.doi.org/10.13182/NSE72-A22549

Analytical Treatment of Neutron Age in Perpendicular Direction in Slab Lattices

Kalimullah, K. S. Ram, G. Srikantiah

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 376-384

Technical Note / dx.doi.org/10.13182/NSE72-A22550

The Treatment of Boundary Value Problems in Optically Thick Media by Means of Lie Series

T. Auerbach, W. Hälg, J. Mennig

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 384-387

Technical Note / dx.doi.org/10.13182/NSE72-A22551

Calculations of Cadmium Cutoff Energies

Antanasije Koci

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 387-389

Technical Note / dx.doi.org/10.13182/NSE72-A22552

Note on the Fast Neutron Cross Sections of Palladium

A. B. Smith, P. Lambropoulos, P. Guenther, J. Whalen

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 389-392

Technical Note / dx.doi.org/10.13182/NSE72-A22553

Total Neutron Cross Section of Mylar at Low Energies

C. Castro Madero, F. Kropff, A. Oliva, J. M. Neill

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 392-393

Technical Note / dx.doi.org/10.13182/NSE72-A22554

Specification and Testing of Nuclear Data Required for Monte Carlo Transport Calculations

E. D. Cashwell, E. F. Plechaty

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 394-395

Technical Note / dx.doi.org/10.13182/NSE72-A22555

The Validity of Using Only Primary Protons in Van Allen Belt and Solar-Flare Proton Shielding Studies

R. T. Santoro, R. G. Alsmiller, Jr., J. Barish

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 395-398

Technical Note / dx.doi.org/10.13182/NSE72-A22556

Laminar- and Slug-Flow Heat Transfer Characteristics of Fuel Rods Adjacent to Fuel Subassembly Walls

Chia-Jung Hsu

Nuclear Science and Engineering / Volume 49 / Number 3 / November 1972 / Pages 398-404

Technical Note / dx.doi.org/10.13182/NSE72-A22557

Number 4

Table of Contents
TASK: A Generalized One-Dimensional Transport and Diffusion Kinetics Code(A. R. Buhl, H. L. Dodds, Jr., J. C. Robinson, R. A. Lillie)
Comments on Temperature-Dependent Intermediate Neutron Resonance Integrals(Yukio Ishiguro)
Reply to “Comments on Temperature-Dependent Intermediate Neutron Resonance Integrals”(Rubin Goldstein)
Reactivity Coefficients in Large Fast Power Reactors(F. Storrer)
Analyses of Temperature and Power Noise in Operating Nuclear Reactors(Keiichi Saito)
Subject Index
The Yield Stress Radiation Damage Function of Iron(G. R. Odette, T. O. Ziebold)

Radiation Transport in a Halfspace with a Source External to the Medium

G. C. Pomraning

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 409-417

Technical Paper / dx.doi.org/10.13182/NSE72-A22561

Time-Dependent Leakage Neutron Spectrum Studies of Some Small Hydrogenous Moderators

Kingsley F Graham, John M. Carpenter

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 418-437

Technical Paper / dx.doi.org/10.13182/NSE72-A22562

An Investigation of Non-Exponential Decay of Neutron Distributions in Graphite

Harold F. McFarlane

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 438-449

Technical Paper / dx.doi.org/10.13182/NSE72-A22563

The Probability Table Method for Treating Unresolved Neutron Resonances in Monte Carlo Calculations

Leo B. Levitt

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 450-457

Technical Paper / dx.doi.org/10.13182/NSE72-3

A New Method for Analysis of Pulsed Fast Neutron Experiments

Shin-ichi Ito

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 458-467

Technical Paper / dx.doi.org/10.13182/NSE72-A22565

Reactivity Worths of Boron, Tantalum, and Europium in a Fast Reactor Spectrum

R. J. Tuttle, T. H. Springer

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 468-481

Technical Paper / dx.doi.org/10.13182/NSE72-A22566

Reactor Depletion Analyzed as a Space-Time Problem

William J. Westlake, Jr., A. F. Henry

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 482-488

Technical Paper / dx.doi.org/10.13182/NSE72-A22567

Criticality of Graphite- and Polyethylene-Reflected Uranium (93.2%)-Metal Cylinders and Annuli

J. T. Mihalczo

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 489-504

Technical Paper / dx.doi.org/10.13182/NSE72-A22568

A Fitting Function for Energy Dissipation Curves of Fast Electrons

Tatsuo Tabata, Rinsuke Ito, Shigeru Okabe

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 505-506

Technical Notes / dx.doi.org/10.13182/NSE72-A22569

Temperature Dependence of Uranium Carbide Fission-Gas Swelling: An Analytical Evaluation

Alan J. Markworth

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 506-507

Technical Notes / dx.doi.org/10.13182/NSE72-A22570

Exact Collision Probabilities for Spherical Shells in a Homogeneous Medium

Tomas Lefvert

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 507-509

Technical Notes / dx.doi.org/10.13182/NSE72-A22571

The Transverse Diffusion Coefficient in a Square Lattice

T. Auerbach, W. Hälg, J. Mennig

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 509-515

Technical Notes / dx.doi.org/10.13182/NSE72-A22572

Optimization of Control Rod Programming and Loading Pattern in Multiregion Nuclear Reactor by the Method of Approximation Programming

Hiroshi Motoda

Nuclear Science and Engineering / Volume 49 / Number 4 / December 1972 / Pages 515-524

Technical Notes / dx.doi.org/10.13182/NSE72-A22573