Home / Publications / Journals / Nuclear Science and Engineering / Volume 47

Volume 47

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Table of Contents
REPP(R. M. Hiatt)
QX1: A One-Dimensional Multigroup Kinetics Program(Daniel A. Meneley, E. S. Wiener, Karl O. Ott)
SN35(M. Pavelescu, V. Anton, I. Purica)
APEL(M. Pavelescu, V. Anton, I. Purica)
“On the Use of Acoustic Waves in Nuclear Power Reactors to Determine Average Void Fractions”(J. A. Bonnet, Jr., R. K. Osborn)
“A Three-Dimensional Stochastic Gamma-Ray Transport Method for Shielding Calculations”(Arsalan Razani, H. E. Hungerford)
“The Effect of Anisotropic Scattering Upon the Elastic Moderation of Fast Neutrons”(W. M. Stacey, Jr.)
“Matrix Riemann-Hilbert Problems Related to Neutron Transport Theory”(E. E. Burniston, C. E. Siewert, P. Silvennoinen, P. F. Zweifel)

Gamma-Ray Albedo Calculations Using Moments Method

C. V. Smith, N. E. Scofield

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 1-7

Technical paper / dx.doi.org/10.13182/NSE72-A28415

A Comparison of Calculated and Measured Yields of Neutron-Energy-Dependent Capture Gamma Rays From Uranium-238

R. S. Booth, J. E. White, S. K. Penny, K. J. Yost

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 8-18

Technical paper / dx.doi.org/10.13182/NSE72-A28416

Fast Neutron Total and Scattering Cross Sections of Plutonium-240

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

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 19-28

Technical paper / dx.doi.org/10.13182/NSE72-A28417

The Effect of Wide Scattering Resonances on Neutron Multigroup Cross Sections

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 29-39

Technical paper / dx.doi.org/10.13182/NSE72-A28418

Determination of Neutron Multiplication Factors as a Function of Temperature with the High Temperature Lattice Test Reactor

C. R. Richey, T. J. Oakes

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 40-58

Technical paper / dx.doi.org/10.13182/NSE72-A28419

Benchmark Gas Core Critical Experiment

J. F. Kunze, J. H. Lofthouse, C. G. Cooper, R. E. Hyland

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 59-65

Technical paper / dx.doi.org/10.13182/NSE72-A28420

Improvements to Neutron Slowing Down Theory for Fast Reactors

Floyd E. Dunn, Martin Becker

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 66-82

Technical paper / dx.doi.org/10.13182/NSE72-A28421

The Formulation and Application of Analytic Representations of Fast Reactor Flux and Importance Spectra

Floyd E. Dunn, Martin Becker

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 83-103

Technical paper / dx.doi.org/10.13182/NSE72-A28422

The Concept of Multiple-Input Zero Power Describing Functions in Nuclear Reactors

A. Z. Akcasu, C. M. Bost, Jr.

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 104-115

Technical paper / dx.doi.org/10.13182/NSE72-A28423

Anisotropic Diffusion Coefficient in Generalized X, Y Geometry: Theory and Application to Diffusion Codes

M. Michelini

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 116-126

Technical paper / dx.doi.org/10.13182/NSE72-A28424

Safety Effects of Light Water Infiltration in the Argonne Research Reactor (CP-5)

Charles N. Kelber

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 127-131

Technical paper / dx.doi.org/10.13182/NSE72-A28425

Physical Properties of the“Once Through Then Out” Pebble-Bed Reactor

U. Hansen, R. Schulten, E. Teuchert

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 132-139

Technical paper / dx.doi.org/10.13182/NSE72-A28426

The Hot Channel Factor as Determined by the Permissible Number of Hot Channels in the Core

P. L. Arnsberger, M. Mazumdar

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 140-149

Technical paper / dx.doi.org/10.13182/NSE72-A28427

A Dead Time Correction for Gamma-Ray Spectroscopy

W. Filippone, F. J. Munno

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 150-151

Technical Note / dx.doi.org/10.13182/NSE72-A28428

The Thermal-Neutron Capture Cross Section and Resonance Capture Integral of Krypton-80

James G. Bradley, Walter H. Johnson

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 151-153

Technical Note / dx.doi.org/10.13182/NSE72-A28429

Steady-State Neutron Spectra in Ice in the Temperature Range 268 to 4°K

G. S. Gangwani, S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 153-156

Technical Note / dx.doi.org/10.13182/NSE72-A28430

Two-Group Neutron Transport Theory with Anisotropic Scattering

R. J. Reith, Jr., C. E. Siewert

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Pages 156-162

Technical Note / dx.doi.org/10.13182/NSE72-A28431

MOD-5 A Discrete Markov Slowing Down Code

T. J. Williamson

Nuclear Science and Engineering / Volume 47 / Number 1 / January 1972 / Page 164

Computer Code Abstract / dx.doi.org/10.13182/NSE72-A28433

Number 2

Table of Contents
NOISY 1: A Program for Calculation of Space-Dependent Spectral Densities in Cubical Reactors(James R. Sheff)
PICA(T. A. Gabriel, M. P. Guthrie, O. W. Hermann)
VENUS: A Two-Dimensional LMFBR Disassembly Computer Program(W. T. Sha)
The Resonance Capture Integral of Holmium-165(L. Le Sage, R. Sher)
Comment on The Resonance Capture Integral of Holmium-165(Thomas E. Stephenson, A. M. Ferrer)
Perturbation Methods in Nuclear Reactors from the Importance Conservation Principle(A. Gandini)

Distribution of Uranyl Nitrate and Nitric Acid Between Aqueous Solutions and 30 Volume Percent Tributyl Phosphate in Hydrocarbon Diluent

Stephen M. Goldberg, Manson Benedict, Hans W. Levi

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 169-186

Technical Paper / dx.doi.org/10.13182/NSE72-A22394

Use of Statistical Theory of Extremes in Hot Channel Analysis of a Liquid Metal Fast Breeder Reactor

M. Mazumdar

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 187-194

Technical Paper / dx.doi.org/10.13182/NSE72-A22395

Error Estimates in Reactor Theory

Yigal Ronen

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 195-202

Technical Paper / dx.doi.org/10.13182/NSE72-A22396

Fission Cross Sections for Five Isotopes of Curium and Californium-249

R. W. Benjamin, K. W. MacMurdo, J. D. Spencer

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 203-208

Technical Paper / dx.doi.org/10.13182/NSE72-A22397

Neutron Energy-Dependent Capture Gamma-Ray Yields in Tantalum and Tungsten

K. J. Yost, J. E. White, C. Y. Fu, W. E. Ford, III

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 209-220

Technical Paper / dx.doi.org/10.13182/NSE72-A22398

The Air-Ground Interface Problem for Disk Isotropic Cobalt-60 Sources

R. M. Rubin

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 221-224

Technical Paper / dx.doi.org/10.13182/NSE72-A22399

The Influence of a Liquid Metal Fast Breeder Reactor Environment on Incipient Boiling Superheat

Robert E. Holtz, Hans K. Fauske, Donald T. Eggen

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 225-228

Technical Note / dx.doi.org/10.13182/NSE72-A22400

Additional Measurements of the Ratio of the Fission Cross Sections of Plutonium-239 and Uranium-235

W. P. Poenitz

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 228-230

Technical Note / dx.doi.org/10.13182/NSE72-A22401

Some Implications of a Stochastic Neutron Population Model with Feedback

Donald J. Dudziak

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 230-234

Technical Note / dx.doi.org/10.13182/NSE72-A22402

Calculation of Reactivity Perturbations with the Monte Carlo Method

W. Matthes

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 234-237

Technical Note / dx.doi.org/10.13182/NSE72-A22403

On Semigroup Theory and Its Application to Space-Time Nuclear Reactor Dynamics

Raymond M. Crawford, William E. Kastenberg

Nuclear Science and Engineering / Volume 47 / Number 2 / February 1972 / Pages 238-241

Technical Note / dx.doi.org/10.13182/NSE72-A22404

Number 3

Table of Contents
Comment on the Existence of a Measured Discontinuity in the Thermal-Neutron Diffusion Coefficient Across the Ice-Water Phase Transition(Peter M. Williams)
Comments on Application of Nonlinear Programming(Daniel Tabak)
Reply to “Comments on Application of Nonlinear Programming”(Gregory F. Malan)

Small-Sample Doppler Effect Measurements and their Interpretation in Fast Reactor Spectra

L. Barleon, E. A. Fischer

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 247-261

Technical Paper / dx.doi.org/10.13182/NSE72-A22412

The Formulation and Application of the Transfer-Scattering Matrix Method to Space-, Energy-, and Angular-Dependent Fast Reactor Kinetics

H. L. Dodds, Jr., J. C. Robinson, A. R. Buhl

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 262-274

Technical Paper / dx.doi.org/10.13182/NSE72-A22413

A Hybrid Method for Solving the Reactor Space-Time-Dependent Equations

D. Saphier

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 275-289

Technical Paper / dx.doi.org/10.13182/NSE72-A22414

Static and Dynamic Experiments with a Repetitively Pulsed Neutron Booster

John T. Mihalczo

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 290-301

Technical Paper / dx.doi.org/10.13182/NSE72-A22415

The Application of the Finite Element Method to the Multigroup Neutron Diffusion Equation

L. A. Semenza, E. E. Lewis, E. C. Rossow

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 302-310

Technical Paper / dx.doi.org/10.13182/NSE72-A22416

The Measurement of Total Delayed-Neutron Yields as a Function of the Energy of the Neutron Inducing Fission

M. S. Krick, A. E. Evans

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 311-318

Technical Paper / dx.doi.org/10.13182/NSE72-A22417

Heterogeneous Method for Calculating Long Term Reactivity Change in a Reactor Including Burnable Poison Rods

Hisashi Hishida, Tamotsu Sekiya

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 319-328

Technical Paper / dx.doi.org/10.13182/NSE72-A22418

Experimental and Analytical Studies of Fast Neutron Transport in Iron

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

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 329-348

Technical Paper / dx.doi.org/10.13182/NSE72-A22419

Low Energy Neutron Interactions with Uranium Carbide

C. Lajeunesse, W. E. Moore, M. L. Yeater

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 349-364

Technical Paper / dx.doi.org/10.13182/NSE72-A22420

A Principle of Information Flow for the Treatment of Discontinuities in Synthesis Techniques

Martin Becker

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 365-370

Technical Note / dx.doi.org/10.13182/NSE72-A22421

Addendum to Note on Subcritical Reactivity from Reactor Noise

Medhat M. El-Zeftawy, Lawrence Ruby

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 370-371

Technical Note / dx.doi.org/10.13182/NSE72-A22422

Thermal-Neutron Capture Cross Section and Resonance Integral for 10.7-Year Krypton-85

C. E. Bemis, Jr., R. E. Druschel, J. Halperin, J. R. Walton

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 371-372

Technical Note / dx.doi.org/10.13182/NSE72-A22423

Measurements of the Total-Neutron Cross-Section Minima in Natural Iron

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

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 372-375

Technical Note / dx.doi.org/10.13182/NSE72-A22424

Last-Collision Model of the Air-Ground Interface Effect on Fast-Neutron Angle Distributions

R. L. French, L. G. Mooney

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 375-380

Technical Note / dx.doi.org/10.13182/NSE72-A22425

Multiregion Analysis of the Effect of Rod Displacement on Heat Transfer in Slug Flow Through Closely Packed Rod Bundles

Chia-Jung Hsu

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 380-388

Technical Note / dx.doi.org/10.13182/NSE72-A22426

Number 4

Table of Contents
Historical Studies in the Physical Sciences(Don M. Yost)
Enrico Fermi, Physicist(Eugene T. Booth)
Principles of Activation Analysis(Vincent P. Guinn)
The Foundations of Neutron Transport Theory(Clarence E. Lee)
The Measurement of Time-Varying Phenomena(Charles E. Cohn)
Comments on the Effect of Transverse Dimensions on the Diffusion Length in Crystalline Moderators(M. M. R. Williams)
Reply to “Comments on the Effect of Transverse Dimensions on the Diffusion Length in Crystalline Moderators”(Feroz Ahmed, L. S. Kothari, Ashok Kumar)

Dynamic Analysis of Reactor Internal Structures with Impact Between Components

George J. Bohm, Amir N. Nahavandi

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 391-408

Technical Paper / dx.doi.org/10.13182/NSE72-A22431

The Response of Covered Silicon Detectors to Monoenergetic Gamma Rays

Melvin Reier

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 409-414

Technical Paper / dx.doi.org/10.13182/NSE72-A22432

Reactor Power Distribution from Analysis of In-Core Detector Readings

M. M. Levine, D. J. Diamond

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 415-420

Technical Paper / dx.doi.org/10.13182/NSE72-A22433

An Investigation of Space-Dependent Reactor Transfer Functions with Temperature Feedback

D. N. Bridges, J. D. Clement

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 421-434

Technical Paper / dx.doi.org/10.13182/NSE72-A22434

The Order of Neutron-Scattering Method in Plane Geometry—One-Velocity Problems

N. Papmehl, Hans J. Zech

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 435-448

Technical Paper / dx.doi.org/10.13182/NSE72-A22435

Variational Flux Synthesis Methods for Multigroup Neutron Diffusion Theory

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 449-469

Technical Paper / dx.doi.org/10.13182/NSE72-A22436

Correlation of Heavy Ion Irradiation Data for Silicon and Gallium Arsenide

W. M. Pritchard

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 470-471

Technical Note / dx.doi.org/10.13182/NSE72-A22437

Effect of the Time Dependence of Fission Product Cross Sections in Fast Reactors

R. E. Schenter, W. L. Bunch, W. W. Little

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 471-472

Technical Note / dx.doi.org/10.13182/NSE72-A22438

A Rigorous Collapse Procedure for Multigroup Neutron Cross Sections

Richard Doyas, Brian Koponen

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 472-475

Technical Note / dx.doi.org/10.13182/NSE72-A22439

Measurement of the Temperature Dependence of k_∞ for a ²³³UO₂-ThO₂ High Temperature Gas-Cooled Reactor Lattice

E. P. Lippincott

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 475-483

Technical Note / dx.doi.org/10.13182/NSE72-A22440

Formulations of Space-Energy-Time Iterative Synthesis

E. L. Fuller

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 483-488

Technical Note / dx.doi.org/10.13182/NSE72-A22441

New Interpretations for the Usachev-Gandini Perturbation Theory

Masaoki Komata

Nuclear Science and Engineering / Volume 47 / Number 4 / April 1972 / Pages 489-493

Technical Note / dx.doi.org/10.13182/NSE72-A22442