Home / Publications / Journals / Nuclear Science and Engineering / Volume 2

Volume 2

Number 1

Table of Contents

Determination of the Neutron Temperature at the Center of the Thermal Test Reactor

G. B. Gavin

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 1-13

dx.doi.org/10.13182/NSE57-A15567

Heat Transfer and Economic Considerations for Selecting Core Sizes and Configurations

R. E. Behmer, B. L. Hoffman

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 14-23

dx.doi.org/10.13182/NSE57-A15568

A Direct Measurement of the Uranium Metal Temperature Coefficient of Reactivity

R. M. Pearce, D. H. Walker

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 24-32

dx.doi.org/10.13182/NSE57-A15569

The Neutron Fissionability of U-239 and Th-233

P. R. Fields, G. L. Pyle, W. C. Bentley

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 33-37

dx.doi.org/10.13182/NSE57-A15570

Mechanism of Dimensional Instability of Uranium

L. L. Seigle, A. J. Opinsky

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 38-48

dx.doi.org/10.13182/NSE57-A15571

Fast Neutron Damaging in Nuclear Reactors. I. Radiation Damage Monitoring with the Electrical Conductivity of Graphite

W. Primak, L. H. Fuchs

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 49-56

dx.doi.org/10.13182/NSE57-A15572

The Preparation of Anhydrous Thorium Tetrachloride

O. C. Dean, J. M. Chandler

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 57-72

dx.doi.org/10.13182/NSE57-A15573

Transient Conduction in Nuclear Reactor Fuel Elements

Lloyd G. Alexander

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 73-86

dx.doi.org/10.13182/NSE57-A15574

Neutron Temperature Measurements in Graphite

M. Küchle

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 87-95

dx.doi.org/10.13182/NSE57-A15575

Experimental Study of Transient Behavior in a Subcooled, Water-Moderated Reactor

F. Schroeder, S. G. Forbes, W. E. Nyer, F. L. Bentzen, G. O. Bright

Nuclear Science and Engineering / Volume 2 / Number 1 / February 1957 / Pages 96-115

dx.doi.org/10.13182/NSE57-A15576

Number 2

Table of Contents
Two-Group Iteration Method for Annular Cylinders(CHARLES N. KELBER, BERNARD I. SPINRAD)
The Modal Non-escape Probability of Neutrons for Convex Bodies(G. W. ANTHONY)
Fission Product Recoil Separation in Suspension Reactors(M. E. A. HERMANS, TH.V.D. PLAS)

Fast Neutron Damaging in Nuclear Reactors. II. The Radiation Damage Function of Graphite

W. PRIMAK

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 117-125

Technical Paper / dx.doi.org/10.13182/NSE57-A25381

Radioactive Carry-Over from Borax-III and Test Systems

ARTHUR J. SHOR, HENRY T. WARD, DAVID MILLER, WALTON A. RODGER

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 126-142

Technical Paper / dx.doi.org/10.13182/NSE57-A25382

Attenuation of 14.1-Mev Neutrons in Water

R. S. CASWELL, R. F. GABBARD, D. W. PADGETT, W. P. DOERING

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 143-159

Technical Paper / dx.doi.org/10.13182/NSE57-A25383

Engineering Data for Diphenyl Cooled Nuclear Reactors

L. W. FROMM , KERMIT ANDERSON

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 160-169

Technical Paper / dx.doi.org/10.13182/NSE57-A25384

Spatial Distribution of Thermal Neutrons from an N¹⁷ Source in Water

KALMAN SHURE, PAUL A. ROYS

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 170-180

Technical Paper / dx.doi.org/10.13182/NSE57-A25385

Measurement of Local Heat Transfer Coefficients with Sodium-Potassium Eutectic in Turbulent Flow

K. D. KUCZEN, T. R. BUMP

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 181-198

Technical Paper / dx.doi.org/10.13182/NSE57-A25386

Neutron Thermalization: II. Heavy Crystalline Moderator

MARK NELKIN

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 199-212

Technical Paper / dx.doi.org/10.13182/NSE57-A25387

Thermal Stresses in Clad Fuel Plates

CHARLES O. SMITH

Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 213-218

Technical Paper / dx.doi.org/10.13182/NSE57-A25388

Number 3

Table of Contents

The Neutron Velocity Spectrum in a Heavy Moderator¹

E. RICHARD COHEN

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 227-245

Technical Paper / dx.doi.org/10.13182/NSE57-A25393

Measuring the Ratio of Thermal to Resonance Neutron Densities Using Thick Indium Foils¹

MOSES A. GREENFIELD, ROSCOE L. KOONTZ, ALAN A. JARRETT

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 246-252

Technical Paper / dx.doi.org/10.13182/NSE57-A25394

Criticality and Flux Calculations for Hydrogenous Assemblies

N. C. FRANCIS, H. HURWITZ, JR., P. F. ZWEIFEL

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 253-287

Technical Paper / dx.doi.org/10.13182/NSE57-A25395

Calibration of Control Rods¹

F. J. JANKOWSKI,² D. KLEIN, T. M. MILLER

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 288-302

Technical Paper / dx.doi.org/10.13182/NSE57-A25396

The Use of Fluidized Beds for the Continuous Drying and Calcination of Dissolved Nitrate Salts

A. A. JONKE, E. J. PETKUS, J. W. LOEDING, AND S. LAWROSKI

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 303-319

Technical Paper / dx.doi.org/10.13182/NSE57-A25397

Fast Neutron Damaging in Nuclear Reactors. III. The Radiation Damage Dosage¹

W. PRIMAK

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 320-333

Technical Paper / dx.doi.org/10.13182/NSE57-A25398

Statistical Evaluation of Fission-Product Absorption Cross Sections at Intermediate and High Energies

P. GREEBLER,† H. HURWITZ, JR.,†† M. L. STORM

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 334-351

Technical Paper / dx.doi.org/10.13182/NSE57-A25399

Method of Studying Multi-Region Reactors with an Analog Computer

J. G. BAYLY, R. M. PEARCE

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 352-362

Technical Paper / dx.doi.org/10.13182/NSE57-A25400

Delayed-Neutron Monitors for the Detection of Sheath Failures in Reactor Fuel Rods

C. H. MILLAR, B. W. SARGENT,¹ J. C. HORSMAN

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 363-372

Technical Paper / dx.doi.org/10.13182/NSE57-A25401

The Thermal Spectrum of an Intermediate Assembly

MARK NELKIN

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 373-381

Technical Paper / dx.doi.org/10.13182/NSE57-A25402

Reactors, Hazard vs Power Level

THOMAS J. BURNETT

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 382-393

Technical Paper / dx.doi.org/10.13182/NSE57-A25403

The Wigner-Wilkins Calculated Thermal Neutron Spectra Compared with Measurements in a Water Moderator

HARVEY J. AMSTER

Nuclear Science and Engineering / Volume 2 / Number 3 / May 1957 / Pages 394-404

Technical Paper / dx.doi.org/10.13182/NSE57-A25404

Number 4

Table of Contents
A Dynamic Programming Solution to a Problem in Heavy Water Production(Richard Bellman)
Critical Equation for the Bare Water-Moderated Reactor(R. Wakabayashi, Y. Fukai)
Engineering Test Reactors with Large Central Irradiation Cavities(George Safonov)
Measurement of the Density of Liquid Rubidium(Stanley Cohen)

Refining of Uranium

Bernhard Blumenthal

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 407-426

Technical Paper / dx.doi.org/10.13182/NSE57-A25406

Half-Lives of Radionuclides. I

H. W. Wright, E. I. Wyatt, S. A. Reynolds, W. S. Lyon, T. H. Handley

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 427-430

Technical Paper / dx.doi.org/10.13182/NSE57-A25407

Effects of Irradiation on Some Corrosion-Resistant Fuel Alloys

J. H. Kittel, S. Greenberg, S. H. Paine, J. E. Draley

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 431-449

Technical Paper / dx.doi.org/10.13182/NSE57-A25408

Prompt Neutron Periods of Metal Critical Assemblies

John D. Orndoff

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 450-460

Technical Paper / dx.doi.org/10.13182/NSE57-A25409

Application of Minimum Loading Conditions to Enriched Lattices

P. L. Hofmann, H. Hurwitz, Jr.

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 461-468

Technical Paper / dx.doi.org/10.13182/NSE57-A25410

Oscillations in the Power Distribution within a Reactor1

A. F. Henry, J. D. Germann

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 469-480

Technical Paper / dx.doi.org/10.13182/NSE57-A25411

On the Effective Capture Cross Section of Pu-240 for Reactor Neutrons

R. W. Stoughton, J. Halperin

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 481-487

Technical Paper / dx.doi.org/10.13182/NSE57-A25412

Resonance Absorption of Neutrons in Metal and Oxide Cylinders

Monte V. Davis

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 488-491

Technical Paper / dx.doi.org/10.13182/NSE57-A25413

Radiation-Induced Decomposition of Thorium Nitrate Solutions

J. W. Boyle, H. A. Mahlman

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 492-500

Technical Paper / dx.doi.org/10.13182/NSE57-A25414

UO₂-NaK Slurry Studies in Loops to 600°C

B. M. Abraham, H. E. Flotow, R. D. Carlson

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 501-512

Technical Paper / dx.doi.org/10.13182/NSE57-A25415

Radiation-Induced Hardness Changes in Graphite

K. E. Horton, R. L. Carter

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 513-515

Technical Paper / dx.doi.org/10.13182/NSE57-A25416

Measurements with a Pulsed Neutron Source

K. H. Beckurts

Nuclear Science and Engineering / Volume 2 / Number 4 / July 1957 / Pages 516-522

Technical Paper / dx.doi.org/10.13182/NSE57-A25417

Number 5

Table of Contents
ANS News(W. W. Grigorieff)

Natural Circulation Steam Generators for Nuclear Power Plants

J. C. Westmoreland

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 533-546

Technical Paper / dx.doi.org/10.13182/NSE57-A25423

Heat Transfer in Fully Developed Flow between Parallel Plates with Variable Heat Sources

Albert L. Loeffler, Jr.

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 547-566

Technical Paper / dx.doi.org/10.13182/NSE57-A25424

Estimation of Fission Product Spectra in Discharged Fuel from Fast Reactors

Ira G. Dillon and Leslie Burris, Jr.

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 567-581

Technical Paper / dx.doi.org/10.13182/NSE57-A25425

Preliminary Design of an LMFR Power Plant

D. Mars, J. N. Inglima, and R. T. Schomer

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 582-601

Technical Paper / dx.doi.org/10.13182/NSE57-A25426

Nondestructive Testing of Reactor Fuel Elements

W. J. McGonnagle

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 602-616

Technical Paper / dx.doi.org/10.13182/NSE57-A25427

Multiple Scattering of Neutrons

G. W. Stuart

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 617-625

Technical Paper / dx.doi.org/10.13182/NSE57-A25428

Monte Carlo Calculation of the Slowing-Down Time Distribution for Neutrons in Hydrogen

George E. Haynam, Marshall F. Crouch

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 626-630

Technical Paper / dx.doi.org/10.13182/NSE57-A25429

Experimental Measurement of the Slowing-Down Time Distribution for Neutrons in Water

Marshall F. Crouch

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 631-639

Technical Paper / dx.doi.org/10.13182/NSE57-A25430

An Experimental Study of Transient Boiling

M. W. Rosenthal

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 640-656

Technical Paper / dx.doi.org/10.13182/NSE57-A25431

Determination of the Ratio of Capture to Fission Cross Sections in EBR-I

P. Kafalas, M. Levenson, C. M. Stevens

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 657-663

Technical Paper / dx.doi.org/10.13182/NSE57-A25432

The Chemical Processing of Two-Region Aqueous Homogeneous Reactors

D. E. Ferguson

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 664-675

Technical Paper / dx.doi.org/10.13182/NSE57-A25433

Resonance Escape Probability Measurements in Th-2% U-235 Light-Water Moderated Lattices

J. P. Phelps, R. Sher

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 676-678

Technical Paper / dx.doi.org/10.13182/NSE57-A25434

Experimental Estimate of the Free Energy of Formation of Plutonium Trifluoride

A. G. Buyers, E. W. MURBACH

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 679-686

Technical Paper / dx.doi.org/10.13182/NSE57-A25435

A General Treatment of Flux Transients

H. D. Brown

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 687-693

Technical Paper / dx.doi.org/10.13182/NSE57-A25436

Transient Pressures in Nuclear Reactors

J. A. Fleck, Jr.

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 694-708

Technical Paper / dx.doi.org/10.13182/NSE57-A25437

Number 6

Table of Contents

Instrumentation in Aircraft for Radiation Measurements

F. J. Davis, P. W. Reinhardt

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 713-727

Technical Paper / dx.doi.org/10.13182/NSE57-A35487

Calculation of Thermal Group Constants for Mixtures Containing Hydrogen

C. D. Petrie, M. L. Storm, P. F. Zweifel

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 728-744

Technical Paper / dx.doi.org/10.13182/NSE57-A35488

Neutron Age in Diphenyl

N. C. Francis, M. L. Storm, P. F. Zweifel

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 745-747

Technical Paper / dx.doi.org/10.13182/NSE57-A35489

Stored Energy in Neutron-Bombarded Graphite

T. J. Neubert, R. B. Lees

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 748-767

Technical Paper / dx.doi.org/10.13182/NSE57-A35490

Uranium Recovery for Spent Fuel by Dissolution in Fused Salt and Fluorination

G. I. Cathers

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 768-777

Technical Paper / dx.doi.org/10.13182/NSE57-A35491

The Diffusion of Uranium into Aluminum

T. K. Bierlein, D. R. Green

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 778-786

Technical Paper / dx.doi.org/10.13182/NSE57-A35492

The Interaction of 0.15- to 1.0-Mev Neutrons with U-238, U-235, and Pu-239

Robert C. Allen

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 787-793

Technical Paper / dx.doi.org/10.13182/NSE57-A35493

Molten Fluorides as Power Reactor Fuels

R. C. Briant, Alvin M. Weinberg

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 797-803

Technical Paper / dx.doi.org/10.13182/NSE57-A35494

The Aircraft Reactor Experiment—Design and Construction

E. S. Bettis, R. W. Schroeder, G. A. Cristy, H. W. Savage, R. G. Affel, L. F. Hemphill

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 804-825

Technical Paper / dx.doi.org/10.13182/NSE57-A35495

The Aircraft Reactor Experiment—Physics

W. K. Ergen, A. D. Callihan, C. B. Mills, Dunlap Scott

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 826-840

Technical Paper / dx.doi.org/10.13182/NSE57-A35496

The Aircraft Reactor Experiment—Operation

E. S. Bettis, W. B. Cottrell, E. R. Mann, J. L. Meem, G. D. Whitman

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 841-853

Technical Paper / dx.doi.org/10.13182/NSE57-A35497

ANS NEWS

W. W . Grigorieff

Nuclear Science and Engineering / Volume 2 / Number 6 / November 1957 / Pages 854-855

dx.doi.org/10.13182/NSE57-A35498