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Volume 14

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Fission Gas Release and Swelling During Heating of Irradiated EBR-II Type Fuel

N. R. CHELLEW, R. K. STEUNENBERG

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE62-A26192

Determination of Fission Product Background in the Gamma Coincidence Technique for U238 Activation Measurements

HECTOR M. ANTÚNEZ

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 8-10

Technical Paper / dx.doi.org/10.13182/NSE62-A26193

Resonance and Total U238 Activation in Thin Natural Uranium-Niobium Fuel Plates

J. J. KEPES, L. A. MIKOLEIT, R. G. SERENKA

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 11-16

Technical Paper / dx.doi.org/10.13182/NSE62-A26194

Penetration and Diffusion of a Beam of Radiation

WILLIAM R. FAUST, ARLO D. ANDERSON

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 17-21

Technical Paper / dx.doi.org/10.13182/NSE62-A26195

Two Group Reactor Kinetics

A. FODERARO, H. L. GARABEDIAN

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 22-29

Technical Paper / dx.doi.org/10.13182/NSE62-A26196

In-Pile Photographic Studies of EBR-II Mark-I and Fermi Core—A Sample Meltdown

C. E. DICKERMAN, G. H. GOLDEN, L. E. ROBINSON

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 30-36

Technical Paper / dx.doi.org/10.13182/NSE62-A26197

Design and Analysis of the Experimental Gas-Cooled Reactor Fuel Assemblies

G. SAMUELS

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 37-52

Technical Paper / dx.doi.org/10.13182/NSE62-A26198

Materials Development for Core I Fuel Assemblies for the Experimental Gas-Cooled Reactor

J. H. COOBS

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 53-68

Technical Paper / dx.doi.org/10.13182/NSE62-A26199

Irradiation Testing of Fuel Materials for EGCR

D. B. TRAUGER

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 69-82

Technical Paper / dx.doi.org/10.13182/NSE62-A26200

Irradiation Effects in the EGCR Fuel

J. G. MORGAN, M. F. OSBORNE, O. SISMAN

Nuclear Science and Engineering / Volume 14 / Number 1 / September 1962 / Pages 83-100

Technical Paper / dx.doi.org/10.13182/NSE62-A26201

Number 2

The Development of High Purity Tantalum and Alloys for Liquid Plutonium Containment in LAMPRE I

Richard M. Bidwell, William E. Ferguson, Calvin C. Burwell, R. Philip Hammond, Keith V. Davidson, Walter R. Wykoff, Robert W. Anderson

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 109-122

Technical Paper / dx.doi.org/10.13182/NSE62-A28110

Corrosion Testing and Fuel Selection for LAMPRE I

C. C. Burwell, R. M. Bidwell, R. P. Hammond, J. E. Kemme, and B. J. Thamer

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 123-134

Technical Paper / dx.doi.org/10.13182/NSE62-A28111

Fabrication of Tantalum Fuel Containers for the LAMPRE I Molten Plutonium Reactor

G. S. Hanks, R. S. Kirby, J. M. Taub

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 135-143

Technical Paper / dx.doi.org/10.13182/NSE62-A28112

Fit of Yankee Startup Experiment Data to a Simple Reactor Analysis Model

Wm. Howard Arnold, Jr.

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 144-152

Technical Paper / dx.doi.org/10.13182/NSE62-A28113

The Measurement of Dynamic Nuclear Reactor Parameters Using the Variance of the Number of Neutrons Detected

Robert W. Albrecht

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 153-158

Technical Paper / dx.doi.org/10.13182/NSE62-A28114

Thermodynamics of Extraction of Nitric Acid by Tri-n-Butyl Phosphate—Hydrocarbon Diluent Solutions: III. Comparison of Literature Data

Wallace Davis, Jr.

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 174-178

Technical Paper / dx.doi.org/10.13182/NSE62-A28117

Determination of Diffusion Coefficients for Thermal Neutrons in D2O at 20, 100, 165, and 220°C

Norman P. Baumann

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 179-185

Technical Paper / dx.doi.org/10.13182/NSE62-A28118

Radiation of an Extended Source

M. J. Barrett

Nuclear Science and Engineering / Volume 14 / Number 2 / October 1962 / Pages 186-191

Technical Paper / dx.doi.org/10.13182/NSE62-A28119

Number 3

Cavitation and Erosion Damage and Damage Particle-Size Measurements with Radioisotopes

William J. Walsh, Frederick G. Hammitt

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 217-223

dx.doi.org/10.13182/NSE62-A26209

Determination of Diffusion Hardening in Water

Eugene Starr, Juan Koppel

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 224-229

dx.doi.org/10.13182/NSE62-A26210

Uranium Powder Ignition Studies

Marvin Tetenbaum, Larry Mishler, Glenn Schnizlein

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 230-238

dx.doi.org/10.13182/NSE62-A26211

The Dancoff Correction in Gap Geometry

W. Rothenstein J. Helholtz

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 239-243

dx.doi.org/10.13182/NSE62-A26212

Resonance Absorption of Neutrons In Lumps with Nonuniform Temperature Distributions

Joel H. Ferziger

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 244-248

dx.doi.org/10.13182/NSE62-A26213

Coincidence Counting of Special Samples

R. F. Overman

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 249-253

dx.doi.org/10.13182/NSE62-A26214

Diffusion Anisotropy in Singly- and Doubly-Periodic Lattices

J. R. Beeler

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 254-265

dx.doi.org/10.13182/NSE62-A26215

An Analytic Approach to Two-Dimensional Reactor Theory

H. L. Garabedian, D. H. Thomas

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 266-271

dx.doi.org/10.13182/NSE62-A26216

A Digital Computer Analysis of Loss-of-Coolant Accident for a Multicircuit Core Nuclear Power Plant

Amir N. Nahavandi

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 272-286

dx.doi.org/10.13182/NSE62-A26217

The Mechanism of Extraction by Tributyl Phosphate—n-Hexane Solvents: Part I. Water Extraction

Donald R. Olander, Manson Benedict

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 287-294

dx.doi.org/10.13182/NSE62-A26218

Discrete Ordinate Quadratures for Thin Slab Cells

David Meneghetti

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 295-303

dx.doi.org/10.13182/NSE62-A26219

Analysis of the Sodium Reactor Experiment Prompt Power Coefficient

C. W. Griffin

Nuclear Science and Engineering / Volume 14 / Number 3 / November 1962 / Pages 304-311

dx.doi.org/10.13182/NSE62-A26220

Number 4

Measurement of Void Fractions in Parallel Rod Arrays

Richard A. Condon, Neil C. Sher

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 327-338

Technical Paper / dx.doi.org/10.13182/NSE62-A26239

The Effect of Rotational Freedom in Several Ammonium Salts and Dimethyl Acetylene on the Inelastic Scattering of Slow Neutrons

J. J. Rush, G. J. Safford, T. I. Taylor, W. W. Havens, Jr.

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 339-345

Technical Paper / dx.doi.org/10.13182/NSE62-A26240

Renewal Theory and the Slowing Down of Neutrons

Coleridge A. Wilkins

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 346-357

Technical Paper / dx.doi.org/10.13182/NSE62-A26241

The Effective U238 Resonance Capture Integrals of Uranium Metal and UO2 Rods

J. Hardy, Jr., G. G. Smith, D. Klein

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 358-365

Technical Paper / dx.doi.org/10.13182/NSE62-A26242

Some Experimental Results Pertinent to Equivalence Relations for Effective Resonance Integrals

J. Hardy, Jr., D. Klein, G. G. Smith

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 366-370

Technical Paper / dx.doi.org/10.13182/NSE62-A26243

Closed Loop Dynamics of Nuclear Rocket Engines with Bleed Turbine Drive

Harold P. Smith, Jr.

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 371-379

Technical Paper / dx.doi.org/10.13182/NSE62-A26244

Mean-Square Error Minimization of Boiling Reactor Noise

Lynn E. Weaver, Kenneth R. Katsma

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 380-383

Technical Paper / dx.doi.org/10.13182/NSE62-A26245

Comparative Performance of Black vs. Gray Control Rods in the Engineering Test Reactor

E. E. Burdick, D. G. Proctor

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 384-389

Technical Paper / dx.doi.org/10.13182/NSE62-A26246

Resonance Absorption in Materials with Grain Structure

R. K. Lane, L. W. Nordheim, J. B. Sampson

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 390-396

Technical Paper / dx.doi.org/10.13182/NSE62-A26247

Neutron Diffractometer Measurement of the Slow Neutron Spectrum from a Modified Split Reactor Core

G. A. Ferguson, Jr., R. H. VOgt

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 397-400

Technical Paper / dx.doi.org/10.13182/NSE62-A26248

A Generalized Variational Method for Reactor Analysis

Alfred L. Mowery, Jr., Raymond L. Murray

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 401-413

Technical Paper / dx.doi.org/10.13182/NSE62-A26249

Void Measurement by the (γ, n) Reaction

S. Zia Rouhani

Nuclear Science and Engineering / Volume 14 / Number 4 / December 1962 / Pages 414-419

Technical Paper / dx.doi.org/10.13182/NSE62-A26250