Home / Publications / Journals / Nuclear Technology / Volume 16 / Number 1

Volume 16

Number 1

Table of Contents
Authors(W. E. Roake, T. T. Claudson, R. L. Simons, W. N. McElroy, L. D. Blackburn, S. D. Harkness, R. Grappel, S. G. McDonald, J. L. Straalsund, G. L. Guthrie, E. E. Bloom, J. R. Weir, Jr., W. G. Wolfer, J. P. Foster, F. A. Garner, P. J. Ring, K. D. Challenger, H. J. Busboom, L. A. Neimark, J. D. B. Lambert, W. F. Murphy, C. W. Renfro, B. F. Rubin, T. J. Black, W. K. Appleby, J. D. Stephen, R. F. Hilbert, T. D. Gulden, C. L. Smith, D. P. Harmon, W. W. Hudritsch, M. Coquerelle, J. Gabolde, R. Lesser, P. Werner, W. J. Lackey, F. J. Homan, A. R. Olsen, M. Conte, M. Mouchnino, F. K. Schmitz, B. L. Harbourne, M. S. Beck, J. P. Foster, A. Biancheria, W. H. McCarthy, K. J. Perry, G. R. Hull, J. W. Bennett, R. J. Beaver, A. E. Richt, O. M. Stansfield, G. E. Russcher, A. L. Pitner, F. J. Homan, G. L. Copeland, R. G. Donnelly, W. R. Martin, J. A. Basmajian, A. L. Pitner, D. E. Mahagin, H. C. F. Ripfel, D. E. Baker, W. E. Ray, R. L. Miller, S. L. Schrock, G. A. Whitlow, E. Berkey, G. G. Sweeney, W. M. Hickam, L. D. Blackburn, J. C. Tobin, R. A. Moen, D. J. Ayres, T. M. Cullen, C. R. Brinkman, G. E. Korth, R. R. Hobbins, J. M. Steichen, Lee A. James, A. J. Lovell, W. E. Pennell)
Preface: Reactor Materials Performance(W. E. Roake (Program Chairman), T. T. Claudson (General Chairman))

Damage Function Analysis of Austenitic-Steel Neutron-Induced Mechanical Property Change Data

R. L. Simons, W. N. McElroy, L. D. Blackburn

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 14-24

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31171

SCIM—A Theory Based Computer Code for the Prediction of the In-Pile Behavior of Type 304 Stainless Steel

S. D. Harkness, R. Grappel, S. G. McDonald

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 25-35

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31172

An Analysis of the Effects of Hydrostatic Stress on Swelling

J. L. Straalsund, G. L. Guthrie

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 36-44

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31173

Effect of Neutron Irradiation on the Ductility of Austenitic Stainless Steel

E. E. Bloom, J. R. Weir, Jr.

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 45-54

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31174

The Interrelationship Between Swelling and Irradiation Creep

W. G. Wolfer, J. P. Foster, F. A. Garner

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 55-63

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31175

An Evaluation of the Effect of Intergranular Attack on Fuel Pin Burst Properties

P. J. Ring, K. D. Challenger, H. J. Busboom

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 64-74

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31176

Performance of Mixed-Oxide Fuel Elements to 11 at.% Burnup

L. A. Neimark, J. D. B. Lambert, W. F. Murphy, C. W. Renfro

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 75-88

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31177

Fuel-Cladding Mechanical Interaction in LMFBR Fuel Rods

B. F. Rubin, T. J. Black, W. K. Appleby, J. D. Stephen, R. F. Hilbert

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 89-99

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31178

The Mechanical Design of TRISO-Coated Particle Fuels for the Large HTGR

T. D. Gulden, C. L. Smith, D. P. Harmon, W. W. Hudritsch

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 100-109

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31179

High Burnup Mixed-Oxide Fuel Irradiation Experiments

M. Coquerelle, J. Gabolde, R. Lesser, P. Werner

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 110-119

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31180

Porosity and Actinide Redistribution During Irradiation of (U, Pu)O₂

W. J. Lackey, F. J. Homan, A. R. Olsen

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 120-142

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31181

Postirradiation Observations of Mixed Oxides with Initial Addition of Fission Product Elements

M. Conte, M. Mouchnino, F. K. Schmitz

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 143-155

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31182

The Development of CYGRO-F for Fuel Rod Behavior Analysis

B. L. Harbourne, M. S. Beck, J. P. Foster, A. Biancheria

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 156-170

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31183

Examination of F3A Series Unencapsulated Mixed-Oxide Fuel Pins Irradiated in EBR-II

W. H. McCarthy, K. J. Perry, G. R. Hull, J. W. Bennett

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 171-186

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31184

Boron Concentration Gradient for Improved Thermal Reactor Performance of Boron-Stainless-Steel Control Rods

R. J. Beaver, A. E. Richt

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 187-196

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31185

Irradiation-Induced Dimensional Change in Boronated Graphite

O. M. Stansfield

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 197-207

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31186

Empirical Helium Release Function from Thermal Reactor Irradiated Boron Carbide

G. E. Russcher, A. L. Pitner

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 208-215

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31187

Performance Modeling of Neutron Absorbers

F. J. Homan

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 216-225

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31188

Irradiation Behavior of Boron Carbide

G. L. Copeland, R. G. Donnelly, W. R. Martin

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 226-237

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31189

Irradiation Effects in Boron Carbide Pellets Irradiated in Fast Neutron Spectra

J. A. Basmajian, A. L. Pitner, D. E. Mahagin, H. C. F. Ripfel, D. E. Baker

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 238-248

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31190

The Structure of Sodium Corrosion Deposits and Their Effect on Heat Transfer Coefficients

W. E. Ray, R. L. Miller, S. L. Schrock, G. A. Whitlow

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 249-262

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31191

Sodium Corrosion and Mass Transfer Analysis with an Ion Probe Mass Spectrometer

E. Berkey, G. G. Sweeney, W. M. Hickam

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 263-277

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31192

Materials Creep Behavior and Elevated Temperature Design

L. D. Blackburn, J. C. Tobin, R. A. Moen

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 278-286

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31193

Creep Data Acquisition and Application to Reactor Component Design

D. J. Ayres, T. M. Cullen

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 287-296

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31194

Estimates of Creep-Fatigue Interaction in Irradiated and Unirradiated Austenitic Stainless Steels

C. R. Brinkman, G. E. Korth, R. R. Hobbins

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 297-307

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31195

Effect of Irradiation on the Strain Rate Dependence of Type 304 Stainless-Steel Mechanical Properties

J. M. Steichen

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 308-315

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31196

Fatigue-Crack Growth in 20% Cold-Worked Type 316 Stainless Steel at Elevated Temperatures

Lee A. James

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 316-322

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31197

Postirradiation Creep of Annealed Type 316 Stainless Steel

A. J. Lovell

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 323-331

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31198

Structural Materials Aspects of LMFBR Core Restraint System Design

W. E. Pennell

Nuclear Technology / Volume 16 / Number 1 / October 1972 / Pages 332-353

Technical Paper / Reactor Materials Performance / Material / dx.doi.org/10.13182/NT72-A31199