Home / Publications / Journals / Nuclear Science and Engineering / Volume 4

Volume 4

Number 1

Table of Contents
Reactor Transfer Functions: Addendum(M. N. Moore)
ANS News(Octave J. Du Temple)

The Age of Polonium-Beryllium Neutrons in Various Metal-Water Mixtures

Melvin Reier, Felix Obenshain, Robert L. Hellens

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE58-A25515

Neutron Age in Mixtures of D₂O and H₂O

James W. Wade

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 12-24

Technical Paper / dx.doi.org/10.13182/NSE58-A25516

The General Critical Reactor Equations

M. J. Nowak

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 25-43

Technical Paper / dx.doi.org/10.13182/NSE58-A25517

Analysis of Temperatures and Expansions Resulting from Exponential Power Changes in a Reactor

Thomas R. Bump, Ralph W. Seidensticker

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 44-64

Technical Paper / dx.doi.org/10.13182/NSE58-A25518

Control Rod Worth Studies on Seed and Blanket Reactors

W. H. Hartley, R. T. Bayard

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 65-72

Technical Paper / dx.doi.org/10.13182/NSE58-A25519

A System of Obtaining and Reducing Neutron Flux Data from a Critical Assembly

H. A. Morewitz, R. F. Valentine

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 73-81

Technical Paper / dx.doi.org/10.13182/NSE58-A25520

Hydrodynamics of a Liquid Poison Scram System

David Burgreen

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 82-95

Technical Paper / dx.doi.org/10.13182/NSE58-A25521

Suppression of Neutron-Induced Activation Outside a Hydrogenous Shield

Fritz W. Mezger

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 96-111

Technical Paper / dx.doi.org/10.13182/NSE58-A25522

Interstitial Compounds of Irradiated Graphite

G. L. Montet

Nuclear Science and Engineering / Volume 4 / Number 1 / July 1958 / Pages 112-133

Technical Paper / dx.doi.org/10.13182/NSE58-A25523

Number 2

Table of Contents
Flux Disadvantage Factor in Plane Slab Lattices(E. Richard Cohen)
Variational Calculations of Lattice Self-Shielding(Leland S. Bohl, John C. Stewart, Norman C. Francis)
Pipe Thicknesses Which Minimize Stresses Due to Internal Pressure and Gamma Heating(K. R. Merckz)
ANS News(Octave J. Du Temple)

Heat Conduction in Internally Cooled Nuclear Reactors

Roy A. Axford

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 139-154

dx.doi.org/10.13182/NSE58-A15358

Uranium-235 Neutron Cross Sections from a Breit-Wigner Analysis

Devereux L. Kavanagh

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 155-165

dx.doi.org/10.13182/NSE58-A15359

Some Applications of the S_n Method

R. M. Klehn

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 166-179

dx.doi.org/10.13182/NSE58-A15360

The EBR-I Meltdown—Physical and Metallurgical Changes in the Core

J. H. Kittel, M. Novick, R. F. Buchanan

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 180-199

dx.doi.org/10.13182/NSE58-A15361

The Stability of Multipass Reactors

John Mac Phee

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 200-208

dx.doi.org/10.13182/NSE58-A15362

An Analytical Approach to the Diffusion Bonding Problem

Louis S. Castleman

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 209-226

dx.doi.org/10.13182/NSE58-A15363

Fast Neutron Dosimetry in Pile Irradiations

R. Wayne Houston

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 227-238

dx.doi.org/10.13182/NSE58-A15364

Laminar Tube Flow with Arbitrary Internal Heat Sources and Wall Heat Transfer

E. M. Sparrow, R. Siegel

Nuclear Science and Engineering / Volume 4 / Number 2 / August 1958 / Pages 239-254

dx.doi.org/10.13182/NSE58-A15365

Number 3

Table of Contents
Solution of the Time-Dependent Thermal Neutron Diffusion Equation(LaMar I. Deverall)
Critical Measurements on UO₃-H₃PO₄ Solutions(J. C. Allred, P. J. Bendt, R. E. Peterson)
A Contribution to Black Control Rod Worth(Jeffery Lewins)
Absence of Irradiation Growth in Alpha-Uranium above 430°C(M. Balicki)
ANS News

On the Chemistry of the Fission Process in Reactor Fuels Containing UF₄ and UO₂

Mark T. Robinson

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 263-269

Technical Paper / dx.doi.org/10.13182/NSE58-A25527

Xenon Poisoning Kinetics in Gas-Sparged, Molten Fluoride Fueled Nuclear Reactors

Mark T. Robinson

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 270-287

Technical Paper / dx.doi.org/10.13182/NSE58-A25528

The Behavior of Fission Products in Molten Fluoride Reactor Fuels

Mark T. Robinson, William A. Brooksbank, Jr., Samuel A. Reynolds, Henry W. Wright, Thomas H. Handley

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 288-296

Technical Paper / dx.doi.org/10.13182/NSE58-A25529

Determination of k_∞ from Critical Experiments with the PCTR

D. J. Donahue, D. D. Lanning, R. A. Bennett, R. E. Heineman

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 297-321

Technical Paper / dx.doi.org/10.13182/NSE58-A25530

Application of the Absorption Area Method To Three-Group Diffusion Theory Problems

S. Pearlstein

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 322-331

Technical Paper / dx.doi.org/10.13182/NSE58-A25531

Effects of Low-Lying Europium Resonances on the Temperature Defect in Water-Moderated Reactors

D. M. Keaveney, T. J. Krieger, M. L. Storm

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 332-340

Technical Paper / dx.doi.org/10.13182/NSE58-A25532

Effect of Alloying on the Critical Mass of a Plutonium Spherical Fast Reactor

James T. Waber, Mary Repar Kline, Leah K. Johnson

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 341-353

Technical Paper / dx.doi.org/10.13182/NSE58-A25533

Broad Aspects of Absorber Materials Selection for Reactor Control

W. K. Anderson

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 357-372

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25534

Nuclear Requirements for Control Materials

H. E. Stevens

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 373-385

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25535

Discrete Fixed Poison Rods Containing Boron

W. E. Ray, W. A. Neisz, H. W. Cooper

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 386-401

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25536

Boron Containing Control Materials

D. N. Dunning, W. K. Anderson, P. R. Mertens

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 402-414

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25537

Boron Stainless Steel Alloys

L. B. Prus, E. S. Byron, J. F. Thompson

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 415-428

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25538

Materials, Fabrication and Performance of the EBWR Control Rods

Nicholas Balai

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 429-438

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25539

The Use of Boron Carbide for Reactor Control

W. K. Barney, G. A. Sehmel, W. E. Seymour

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 439-448

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25540

Development of a Composite Control Rod

G. W. Cunningham, A. K. Foulds, D. L. Keller, W. E. Ray

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 449-457

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25541

Radiation Damage Resistance of Some Rare Earth Cermets

W. K. Anderson, D. N. Dunning

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 458-466

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25542

New Developments in the Fabrication of Hafnium Control Rods

J. Giacobbe, D. N. Dunning

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 467-480

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25543

A Method of Hot Coextruding Complex Shapes through Round Dies

W. E. Ray, C. J. Beck

Nuclear Science and Engineering / Volume 4 / Number 3 / September 1958 / Pages 481-494

Symposium on Reactor Control Materials / dx.doi.org/10.13182/NSE58-A25544

Number 4

Table of Contents
Two Group Calculation of Prompt Neutron Lifetime(Wm. Howard Arnold, Jr.)
ANS News(Octave J. DuTemple)

The Preparation of Thorium Metal by Sodium Amalgam Reduction of Thorium Chloride: the Metallex Process

O. C. Dean, G. K. Ellis

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 509-521

Technical Paper / dx.doi.org/10.13182/NSE58-A28827

Mutual Shielding of Lattice Pins in the Resonance Energy Region

W. G. Pettus, I. E. Dayton

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 522-529

Technical Paper / dx.doi.org/10.13182/NSE58-A28828

Self-Shielding Experiments with Gaseous and Solid B-10

G.P. Rutledge, R. R. Eggleston

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 530-535

Technical Paper / dx.doi.org/10.13182/NSE58-A28829

Production Cross Section of N⁶ and N^17¹

Paul A. Roys, Kalman Shure

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 536-545

Technical Paper / dx.doi.org/10.13182/NSE58-A28830

Age to Indium Resonance for D-D Neutrons in Water

V. Spiegel, Jr., D. W. Oliver, R. S. Caswell

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 546-562

Technical Paper / dx.doi.org/10.13182/NSE58-A28831

Computing Absolute Thermal Neutron Flux from Measurements Made with Indium Foils

Moses A. Greenfield, Roscoe L. Koontz, Alan A. Jarrett

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 563-569

Technical Paper / dx.doi.org/10.13182/NSE58-A28832

A Remark on Neutron Thermalization Theory

G. Leibfried

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 570-575

Technical Paper / dx.doi.org/10.13182/NSE58-A28833

Total Neutron Cross Sections for Structural Materials

R. J. Brown, L. M. Bollinger

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 576-580

Technical Paper / dx.doi.org/10.13182/NSE58-A28834

The Method of Discrete Ordinates

Gerald Goertzel

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 581-587

Technical Paper / dx.doi.org/10.13182/NSE58-A28835

The Kinetics of Circulating Fuel Reactors

John MacPhee

Nuclear Science and Engineering / Volume 4 / Number 4 / October 1958 / Pages 588-597

Technical Paper / dx.doi.org/10.13182/NSE4-588-597

Number 5

Table of Contents

Heat Transfer in a Cross Flow Nuclear Reactor

Charles L. Larson

Nuclear Science and Engineering / Volume 4 / Number 5 / November 1958 / Pages 607-622

Technical Paper / dx.doi.org/10.13182/NSE58-A25551

Perturbation Integrals for Two Group Calculations and Application to Reflector Ducts

Gene A. Baraff, Raymond L. Murray, A. C. Menius, Jr.

Nuclear Science and Engineering / Volume 4 / Number 5 / November 1958 / Pages 623-634

Technical Paper / dx.doi.org/10.13182/NSE58-A25552

The General Theory of Control Sheets

Bertram Wolfe

Nuclear Science and Engineering / Volume 4 / Number 5 / November 1958 / Pages 635-648

Technical Paper / dx.doi.org/10.13182/NSE58-A25553

Some Refinements in the Calculation of Resonance Integrals

Jack Chernick, Russel Vernon

Nuclear Science and Engineering / Volume 4 / Number 5 / November 1958 / Pages 649-672

Technical Paper / dx.doi.org/10.13182/NSE58-A25554

Effect of In-Pile Local Boiling on Surface Deposition and Corrosion

Kurt Katz, Walter E. Hopkins, Jr.

Nuclear Science and Engineering / Volume 4 / Number 5 / November 1958 / Pages 673-689

Technical Paper / dx.doi.org/10.13182/NSE58-A25555

Variation of Graphite Diffusion Length with Temperature

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

Nuclear Science and Engineering / Volume 4 / Number 5 / November 1958 / Pages 690-697

Technical Paper / dx.doi.org/10.13182/NSE58-A25556

Capture and Fission Patterns of U²³⁸ in EBR-I (Mark II)

P. Kafalas, R. R. Heinrich

Nuclear Science and Engineering / Volume 4 / Number 5 / November 1958 / Pages 698-702

Technical Paper / dx.doi.org/10.13182/NSE58-A25557

Number 6

Table of Contents
Dimensional Stability of Uranium-Chromium Alloys(M. C. Fraser, G. A. Last, S. H. Bush)
High Flux Reactors(Jack Chernick)
ANS News(Octave J. Du Temple)

Prompt Neutron Periods of a Critical Assembly Measured with a Pulsed Source

P. J. Bendt, H. J. Karr, F. R. Scott

Nuclear Science and Engineering / Volume 4 / Number 6 / December 1958 / Pages 703-708

dx.doi.org/10.13182/NSE58-A15492

Isotopic Analysis: Cerium-141 and Cerium-144

W. S. Lyon

Nuclear Science and Engineering / Volume 4 / Number 6 / December 1958 / Pages 709-712

dx.doi.org/10.13182/NSE58-A15493

Fission Power Distribution near a Cruciform Water Gap

E. R. Sanford, H. J. Litre

Nuclear Science and Engineering / Volume 4 / Number 6 / December 1958 / Pages 713-726

dx.doi.org/10.13182/NSE58-A15494

Verification of a Method for Treating Neutron Space-Time Problems

A. F. Henry, N. J. Curlee

Nuclear Science and Engineering / Volume 4 / Number 6 / December 1958 / Pages 727-744

dx.doi.org/10.13182/NSE4-727

Plutonium Fast Power Breeder with Oxide Fuel and Blanket Elements

John B. Sampson, E. A. Luebke

Nuclear Science and Engineering / Volume 4 / Number 6 / December 1958 / Pages 745-761

dx.doi.org/10.13182/NSE58-A15496

Selection of a Reactor Containment Structure

Theodore H. Smith, Burr H. Randolph

Nuclear Science and Engineering / Volume 4 / Number 6 / December 1958 / Pages 762-784

dx.doi.org/10.13182/NSE58-A15497

Perturbation Theory of Control Elements. I

Bertram Wolfe, David L. Fischer

Nuclear Science and Engineering / Volume 4 / Number 6 / December 1958 / Pages 785-793

dx.doi.org/10.13182/NSE58-A15498