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Volume 18

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Number 1

A Differential Calorimeter for Radiation-Induced Power

Wm. Bradley Lewis

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 1-5

Technical Paper / dx.doi.org/10.13182/NSE64-A18136

A Comparison of Methods of Determining Burnup on Uranium Dioxide Fuel Test Specimens

R. G. Hart, M. Lounsbury, R. W. Jones, M. J. F. Notley

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 6-17

Technical Paper / dx.doi.org/10.13182/NSE64-A18137

Titanium and Titanium Alloys in Mercury - Some Observations on Corrosion and Inhibition

James Y. N. Wang

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 18-30

Technical Paper / dx.doi.org/10.13182/NSE64-A18138

Theoretical and Experimental Study of Fatigue in Photomultiplier Tubes

I. Cantarell

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 31-48

Technical Paper / dx.doi.org/10.13182/NSE64-A18139

The Calculation of the Thermal Utilization and Disadvantage Factor in Uranium/Water Lattices

Henry C. Honeck

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 49-68

Technical Paper / dx.doi.org/10.13182/NSE64-A18140

Heat-Transfer Studies of Water Flow in Thin Rectangular Channels: Part I - Heat Transfer, Burnout, and Friction for Water in Turbulent Forced Convection

W. R. Gambill, R. D. Bundy

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 69-79

Technical Paper / dx.doi.org/10.13182/NSE64-A18141

Heat-Transfer Studies of Water Flow in Thin Rectangular Channels: Part II - Boiling Burnout Heat Flux for Low-Pressure Water in Natural Circulation

W. R. Gambill, R. D. Bundy

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 80-89

Technical Paper / dx.doi.org/10.13182/NSE64-A18142

The Application of “One-Group” Transport Theory to β-Ray Dosimetry

K. O'Brien, S. Samson, R. Sanna, J. E. McLaughlin

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 90-96

Technical Paper / dx.doi.org/10.13182/NSE64-A18143

Gas Chromatography as Applied to Nuclear Technology - II. Analysis of the Hydrolysis Products of Uranium Carbides and Thorium Carbides

A. D. Horton, J. L. Botts

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 97-104

Technical Paper / dx.doi.org/10.13182/NSE64-A18144

Reactions O17 (n, p)N17 and O18 (n, d)N17 with Reactor Neutrons

Saadia Amiel, Jacob Gilat

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 105-109

Technical Paper / dx.doi.org/10.13182/NSE64-A18145

Production of Transuranium Elements in a Thermonuclear Explosion - Anacostia

R. W. Hoff, D. W. Dorn

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 110-112

Technical Paper / dx.doi.org/10.13182/NSE64-A18146

Economy of Experiment in Dose Albedo

N. F. Shoemaker, C. M. Huddleston

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 113-115

Technical Paper / dx.doi.org/10.13182/NSE64-A18147

Lattice-Parameter Measurements for Solid and Concentric Tubes of Uranium Fuel in Graphite Lattices

D. E. Wood, K. R. Birney, E. Z. Block

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 116-125

Technical Paper / dx.doi.org/10.13182/NSE64-A18148

Elastic Scattering of Fast Neutrons from U235

A. B. Smith

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 126-129

Technical Paper / dx.doi.org/10.13182/NSE64-A18149

Theoretical Analysis of the Exponential Experiment in Natural Uranium

Paul Michael

Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 130-136

Technical Paper / dx.doi.org/10.13182/NSE64-A18150

Number 2

Release of Fission Products During In-Pile Melting of UO2

W.E. Browning, Jr., C.E. Miller, Jr., R.P. Shields,B.F. Roberts

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 151-162

Technical Paper / dx.doi.org/10.13182/NSE64-1

Application of Synthesis Techniques to Problems Involving Time Dependence

S. Kaplan, O. J. Marlowe, J. Bewick

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 163-176

Technical Paper / dx.doi.org/10.13182/NSE64-A18315

The Recovery of Protactinium and Uranium from Molten Fluoride Systems by Precipitation as Oxides

J. H. Shaffer, W. R. Grimes, G. M. Watson, D. R. Cuneo, J. E. Strain, M. J. Kelly

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 177-181

Technical Paper / dx.doi.org/10.13182/NSE64-A18316

Inelastic Neutron Scattering in Liquid Methane and Liquid Parahydroge

W. L. Whittemore

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 182-188

Technical Paper / dx.doi.org/10.13182/NSE64-A18317

The Leachability of Fission Products from Uranium-Impregnated Graphite Heated at High Temperature

Kazumi Iwamoto

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 189-199

Technical Paper / dx.doi.org/10.13182/NSE64-A18318

Design of a Pressure Balanced Control Rod

F. K. Clements, A. D. Kartchner, R. S. Kern, W. B. Lewis

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 200-206

Technical Paper / dx.doi.org/10.13182/NSE64-A18319

Methods for Determining the Energy Release in Hypothetical Fast-Reactor Meltdown Accidents

Richard B. Nicholson

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 207-219

Technical Paper / dx.doi.org/10.13182/NSE64-A18320

Evaluation of Two-Region-Reactor Parameters by Random Noise Measurements

Allen R. Boynton, Robert E. Uhrig

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 220-229

Technical Paper / dx.doi.org/10.13182/NSE64-A18321

Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity

E. Starr, H. Honeck, J. DeVilliers†

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 230-235

Technical Paper / dx.doi.org/10.13182/NSE64-A18322

Determination of Cadmium Burnup in Reactor Control Rods by Neutron Radiography

Harold Berger, James H. Talboy, Joseph P. Tylka

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 236-241

Technical Paper / dx.doi.org/10.13182/NSE64-A18323

Theory of Pulsing Techniques

Edward Garelis

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 242-245

Technical Paper / dx.doi.org/10.13182/NSE64-A18324

The Effective Resonance Integral of Thorium Oxide Rods

Jakob Weitman

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 246-259

Technical Paper / dx.doi.org/10.13182/NSE64-A18325

The Energy-Dependent Milne Problem with a Simple Scattering Kernel

M. M. R. Williams

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 260-270

Technical Paper / dx.doi.org/10.13182/NSE64-A18326

A Nonlinear Analysis of a Reactor with Two Temperature Coefficients

Louis M. Shotkin

Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 271-279

Technical Paper / dx.doi.org/10.13182/NSE64-A18327

Number 3

Fission-Gas Release from Pyrolytic-Carbon-Coated Fuel Particles During Irradiation

P. E. Reagan, F. L. Carlsen, R. M. Carroll

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 301-318

Technical Paper / dx.doi.org/10.13182/NSE64-A20051

In-Pile Experiments on Meltdown of EBR-II Mark I Fuel Elements in Stagnant Sodium

C. E. Dickerman, E. S. Sowa, J. H. Monaweck, A. Barsell

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 319-328

Technical Paper / dx.doi.org/10.13182/NSE64-A20052

Boundary Conditions for Parallel Channel Flow

J. F. Thorpe

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 329-334

Technical Paper / dx.doi.org/10.13182/NSE64-A20053

A Digital Computer Solution for Space-Dependent Neutron Kinetics Equations

A. N. Nahavandi, R. F. Von Hollen

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 335-350

Technical Paper / dx.doi.org/10.13182/NSE64-A20054

Temperature Dependence of Neutron-Pulse Parameters in H2O

W. W. Clendenin

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 351-362

Technical Paper / dx.doi.org/10.13182/NSE64-A20055

An Eigenvalue Method for the Calculation of Nuclear Burnup

G. D. Joanou, J. R. Triplett, R. M. Wagner

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 363-369

Technical Paper / dx.doi.org/10.13182/NSE64-A20056

An Improved Spherical-Harmonics Method

W. R. Conkie

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 370-375

Technical Paper / dx.doi.org/10.13182/NSE64-A20057

Neutron-Spectrum Measurements in H2O, CH2 and C6H6

J. C. Young, G. D. Trimble, Y. D. Naliboff, D. H. Houston, J. R. Beyster

Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 376-399

Technical Paper / dx.doi.org/10.13182/NSE64-A20058

Number 4

Direct-Contact Core Systems

R. Philip Hammond, John R. Humphreys, Jr.

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 421-425

Technical Paper / dx.doi.org/10.13182/NSE64-A18759

Fission-Product Behavior in Direct-Contact-Core Liquid-Metal-Fueled Reactors

Richard M. Bidwell

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 426-434

Technical Paper / dx.doi.org/10.13182/NSE64-A18760

Delayed Neutron Economy and Control in a Direct-Contact-Core Liquid-Metal-Fueled Reactor

Richard M. Bidwell

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 435-442

Technical Papers / dx.doi.org/10.13182/NSE64-A18761

The Effect of Axial Heat Conduction in Fuel Plates on Maximum Heat Flow Rates and Temperatures

J. R. Fagan, J. O. Mingle

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 443-447

Technical Paper / dx.doi.org/10.13182/NSE64-A18762

Intercomparison of Fast-Neutron Flux Monitors in a Hollow Fuel Element in Pluto

D. M. Clare, W. H. Martin, B. T. Kelly

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 448-458

Technical Paper / dx.doi.org/10.13182/NSE64-A18763

Numerical Integration of the Spherical-Harmonics Equations

H. Waldinger, J. Agresta, G. Goertzel

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 459-467

Technical Paper / dx.doi.org/10.13182/NSE64-A18764

Determination of Fast-Neutron Dose by Nickel Activation

W. H. Martin, D. M. Clare

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 468-473

Technical Paper / dx.doi.org/10.13182/NSE64-A18765

Measurements of Leakage-Neutron Energy Spectra

C. A. Anderson, Jr., T. J. Thompson

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 474-480

Technical Paper / dx.doi.org/10.13182/NSE64-A18766

Reactor Kinetics Analysis by an Inverse Method

Raymond L. Murray, Carroll R. Bingham, Chreston F. Martin

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 481-490

Technical Paper / dx.doi.org/10.13182/NSE64-A18767

Neutron Transport in Cylindrical Rods

K. Bingham Cady, Melville Clark, Jr.

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 491-507

Technical Paper / dx.doi.org/10.13182/NSE64-A18768

Closed-Loop Dynamics of Nuclear Rocket Engines with Topping Turbine Drive

Harold P. Smith, Jr.

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 508-513

Technical Paper / dx.doi.org/10.13182/NSE64-A18769

Fuel-Importance Function and Minimum Critical Mass

Masuhiko Otsuka

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 514-517

Technical Paper / dx.doi.org/10.13182/NSE64-A18770

Treat Study of the Penetration of Molten Uranium and U/5 wt% Fs Alloy through Type 304 Stainless Steel

C. M. Walter, C. E Dickerman

Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 518-524

Technical Paper / dx.doi.org/10.13182/NSE64-A18771