Home / Publications / Journals / Nuclear Science and Engineering / Volume 3

Volume 3

Number 1

Table of Contents
The Doppler Coefficient of U²³⁵ Fuel Elements(MONTE V. DAVIS)
The Magneto-Ionic Expander Isotope Separator Applied to Uranium(JOSEPH SLEPIAN)
Foil Depression Factors for Indium Disk Detectors(TOM L. GALLAGHER)

The Thermal Neutron Spectrum in a Diffusing Medium

H. Hurwitz, Jr.; M.S. Nelkin

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE58-A25440

Fast Neutron Scattering from Thick Slabs

T. D. Strickler, H. E. Gilbert, J. A. Auxier

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 11-18

Technical Paper / dx.doi.org/10.13182/NSE58-A25441

Effects of Irradiation on Corrosion Resistance of Some High Uranium Alloys

Sherman Greenberg, Joseph E. Draley

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 19-28

Technical Paper / dx.doi.org/10.13182/NSE58-A25442

Some Characteristics of the Thermal Neutron Scattering Probability

R. K. Osborn

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 29-37

Technical Paper / dx.doi.org/10.13182/NSE58-A25443

Estimation of Charge Life for Reactors with Small Cores

H. L. McMurray, A. V. Grimaud, G. H. Hanson

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 38-46

Technical Paper / dx.doi.org/10.13182/NSE58-A25444

The Decay of Fission Product Activity for Cyclic Operation of a Reactor

James W. Butler, M. Grotenhuis

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 47-51

Technical Paper / dx.doi.org/10.13182/NSE58-A25445

The Application of Reactor Kinetics to the Analysis of Experiments

A. F. Henry

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 52-70

Technical Paper / dx.doi.org/10.13182/NSE58-1

Neutron Self-Shielding in a Simple Plane Lattice

Joel Bengston

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 71-76

Technical Paper / dx.doi.org/10.13182/NSE58-A25447

A Semiempirical Method of Calculating the Energy Absorption Buildup Factor with an Application to a Uniformly Contaminated Space Having Spherical Boundaries

Keran O'Brien, Wayne M. Lowder, Leonard R. Solon

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 77-84

Technical Paper / dx.doi.org/10.13182/NSE58-A25448

Heat Transfer In Heterogeneous Circulating-Fuel Reactors

H. F. Poppendiek, L. D. Palmer

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 85-106

Technical Paper / dx.doi.org/10.13182/NSE58-A25449

Number 2

Table of Contents

Measurements of the Conversion Ratio of the PWR Critical Facility Blanket

W. Baer, M. J. Galper, N. Carbone

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 113-128

Technical Paper / dx.doi.org/10.13182/NSE58-A25454

Coupled Fast-Thermal Power Breeder

Robert Avery

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 129-144

Technical Paper / dx.doi.org/10.13182/NSE58-A25455

The Production of N¹⁶ and N¹⁷ in the Cooling Water of the NRX Reactor

W. J. Henderson, P. R. Tunnicliffe

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 145-150

Technical Paper / dx.doi.org/10.13182/NSE58-A25456

Ten-Group Calculated Equilibrium Neutron Spectrum and Diffusion Length in Natural Uranium

D. Meneghetti, H. H. Hummel, W. B. Loewenstein

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 151-160

Technical Paper / dx.doi.org/10.13182/NSE58-A25457

On the Multiple Scattering of Neutrons in Hydrogen-like Substances

C. H. Blanchard

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 161-170

Technical Paper / dx.doi.org/10.13182/NSE58-A25458

Reaction Kinetics of Zirconium and Zircaloy-2 in Dry Air at Elevated Temperatures

L. F. Kendall, R. G. Wheeler, S. H. Bush

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 171-185

Technical Paper / dx.doi.org/10.13182/NSE58-A25459

Thin Regions In Diffusion Theory Calculations

Eugene L. Wachspress

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 186-200

Technical Paper / dx.doi.org/10.13182/NSE58-A25460

A Study of the Equilibration Process in the Fast Exponential Experiment

W. A. Reardon, H. H. Hummel

Nuclear Science and Engineering / Volume 3 / Number 2 / February 1958 / Pages 201-213

Technical Paper / dx.doi.org/10.13182/NSE58-A25461

Number 3

Table of Contents
The Age of Polonium-Boron Neutrons in Water(MELVIN REIER)
ANS NEWS(W. W. Grigorieff)

Determination of Reactor Power by Coolant Activity Monitoring

Eugene E. Drucker, William D. Wallace

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 215-231

Technical Paper / dx.doi.org/10.13182/NSE58-A25463

Metallurgical Problems in Fabrication of Zirconium-Clad Fuel Elements for Pressurized Water Reactors

R. B. Gordon

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 232-249

Technical Paper / dx.doi.org/10.13182/NSE58-A25464

Effects of High Burnup on Natural Uranium

J. H. Kittel, S. H. Paine

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 250-268

Technical Paper / dx.doi.org/10.13182/NSE58-A25465

Calculations of Neutron Distributions by the Methods of Stochastic Processes

Carl N. Klahr

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 269-285

Technical Paper / dx.doi.org/10.13182/NSE58-A25466

The Effective Resonance Integral of Thorium and Thorium Oxide

I. E. Dayton, W. G. Pettus

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 286-295

Technical Paper / dx.doi.org/10.13182/NSE58-A25467

Worths of Black Control Rods

WM. Howard Arnold, Jr.

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 296-299

Technical Paper / dx.doi.org/10.13182/NSE58-A25468

The Efficiency of Composite Fins

James J. Barker

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 300-312

Technical Paper / dx.doi.org/10.13182/NSE58-A25469

Two-Dimensional (r,z) Multigroup Calculation for an Intermediate Spectrum Critical Assembly

P. L. Hofmann, M. L. Storm

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 313-338

Technical Paper / dx.doi.org/10.13182/NSE58-A25470

Method of Successive Generations

G. W. Stuart, R. W. Woodruff

Nuclear Science and Engineering / Volume 3 / Number 3 / March 1958 / Pages 339-373

Technical Paper / dx.doi.org/10.13182/NSE58-A25471

Number 4

Table of Contents
An Iterative Method for Solving the P_l Equations in Slab Geometry(E. Gelbard)
ANS NEWS(Fourth Annual Meeting)

Control Rod Drive Mechanism on the EBWR

C. F. Bullinger, W. J. Kann

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 379-386

Technical Paper / dx.doi.org/10.13182/NSE58-A25475

The Determination of Reactor Transfer Functions from Measurements at Steady Operation

M. N. Moore

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 387-394

Technical Paper / dx.doi.org/10.13182/NSE58-A25476

Effective Reactor Cross Sections in MTR Fuel Assemblies

J. Halperin, J. O. Blomeke, D. A. Mrkvicka

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 395-402

Technical Paper / dx.doi.org/10.13182/NSE58-A25477

Measurements of Thermal Utilization, Resonance Escape Probability, and Fast Effect in Water-Moderated, Slightly Enriched Uranium and Uranium Oxide Lattices

D. Klein, A. Z. Kranz, G. G. Smith, W. Baer, J. DeJuren

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 403-427

Technical Paper / dx.doi.org/10.13182/NSE58-A25478

Fission Gas Behavior in the Uranium-Aluminum System

Myron B. Reynolds

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 428-434

Technical Paper / dx.doi.org/10.13182/NSE58-A25479

Slow Neutron Velocity Spectrometer Studies of the Total and Fission Cross Sections of U^{235 1, 2}

E. Melkonian, V. Perez-Mendez, Miriam Levin Melkonian, W. W. Havens, Jr., L. J. Rainwater

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 435-444

Technical Paper / dx.doi.org/10.13182/NSE58-A25480

Control Rod Calculations for Determination of Reactivity and Power Distribution

P. Greebler

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 445-455

Technical Paper / dx.doi.org/10.13182/NSE58-A25481

General Solution of the Reactor Kinetic Equations without Feedback

Ziya Akcasu

Nuclear Science and Engineering / Volume 3 / Number 4 / April 1958 / Pages 456-467

Technical Paper / dx.doi.org/10.13182/NSE58-A25482

Number 5

Table of Contents
Critical Equations for Finite Cylindrical Reactors(G. W. Stuart)
Use of Aluminum as a Threshold Neutron Detector(F. E. Jablonski, A. F. DiMeglio)
Equivalence Factors for D₂O(Charles Kelber)

A Method for the Separation of Plutonium from Uranium

E. Haeffner, Å. Hultgren

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 471-481

Technical Paper / dx.doi.org/10.13182/NSE58-A25486

Kinetics of Homogeneous Power Reactors of the LAPRE Type

John C. Allred, David S. Carter

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 482-503

Technical Paper / dx.doi.org/10.13182/NSE58-A25487

Two-Group Diffusion Theory for a Ring of Cylindrical Rods

R. Avery

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 504-513

Technical Paper / dx.doi.org/10.13182/NSE58-A25488

A Chemical Model of Radiation Damage in Graphite

G. R. Hennig

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 514-528

Technical Paper / dx.doi.org/10.13182/NSE58-A25489

Removal of Decay Heat from a Plate-Type Fuel Subassembly in the Atmosphere

R. E. Grimble, B. W. LeTourneau

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 529-539

Technical Paper / dx.doi.org/10.13182/NSE58-A25490

Thermal Stresses in Externally Clad Cylindrical Fuel Elements

C. O. Smith

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 540-547

Technical Paper / dx.doi.org/10.13182/NSE58-A25491

Reactor Response to Reactivity Changes During a Xenon Transient

H. L. Garabedian, R. S. Varga, G. G. Bilodeau

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 548-572

Technical Paper / dx.doi.org/10.13182/NSE58-A25492

The Transfer Function of a Water Boiler Reactor

R. E. Skinner, D. L. Hetrick

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 573-594

Technical Paper / dx.doi.org/10.13182/NSE58-A25493

A Pulsed Neutron Technique for Reactivity Determination

B. E. Simmons, J. S. King

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 595-608

Technical Paper / dx.doi.org/10.13182/NSE3-595-608

Measurement of the Gamma-Ray Dose near the Interface between Two Media

Frank Titus

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 609-619

Technical Paper / dx.doi.org/10.13182/NSE58-A25495

A High-Frequency Reactor Instability Mechanism

Richard B. Nicholson

Nuclear Science and Engineering / Volume 3 / Number 5 / May 1958 / Pages 620-627

Technical Paper / dx.doi.org/10.13182/NSE58-A25496

Number 6

Table of Contents
Equilibrium Spectrum and Diffusion Length in Natural Uranium(D. Meneghetti, H. H. Hummel, W. B. Loewenstein)
Pipe Thicknesses Which Minimize Stresses Due to Internal Pressure and Gamma Heating(K. R. Merckx)
X-Ray Diffraction Studies of Pile-Irradiated Hafnium Hydrides(S. S. Sidhu, F. P. Campos, D. D. Zauberis)
ANS News

Yvon’s Method for Slabs

S. Zlering, D. Schiff

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 635-647

Technical Paper / dx.doi.org/10.13182/NSE58-A25501

Electronic Analog Simulation of an In-Pile Circulating Fuel Loop

Mark T. Robinson, Joseph F. Krause, Francis P. Green, Donald F. Weekes

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 648-659

Technical Paper / dx.doi.org/10.13182/NSE58-A25502

Radiation Processing of Foods

Raymond J. Beeley

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 660-693

Technical Paper / dx.doi.org/10.13182/NSE58-A25503

Critical Parameters of a Proton-Moderated and Proton-Reflected Slab of U²³⁵

J. K. Fox, L. W. Gilley, J. H. Marable

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 694-697

Technical Paper / dx.doi.org/10.13182/NSE58-A25504

Spatial Distribution of U²³⁸ Resonance Neutron Capture in Uranium Metal Rods

D. Klein, W. Baer, G. G. Smith

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 698-706

Technical Paper / dx.doi.org/10.13182/NSE58-A25505

Effect of Uranium Recycle on Transuranic Element Buildup

E. D. Arnold

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 707-725

Technical Paper / dx.doi.org/10.13182/NSE58-A25506

Energy Release from the Decay of Fission Products

J. F. Perkins, R. W. King

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 726-746

Technical Paper / dx.doi.org/10.13182/NSE58-A25507

The Effective Cross Section of Pu²⁴⁰ in Long-Term Reactivity Calculations

R. L. Crowther, J. W. Weil

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 747-757

Technical Paper / dx.doi.org/10.13182/NSE58-A25508

Subcadmium in-Pile Etas and Absorption Cross Sections of U²³³, Pu²³⁹, and Pu²⁴¹

E. R. Gaerttner, M. E. Jones, D. E. McMillan, J. B. Sampson, T. M. Snyder

Nuclear Science and Engineering / Volume 3 / Number 6 / June 1958 / Pages 758-771

Technical Paper / dx.doi.org/10.13182/NSE58-A25509