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Volume 16

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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

Number 2

Table of Contents
Authors(G. Schileo, C. Lepscky, G. M. Testa, H. Hougaard, K. W. Jones, T. K. Thompson, G. E. Lohse, B. R. Wheeler, J. F. Bates, A. L. Pitner, A. L. Pitner, R. P. Gardner, K. Verghese, J. I. Cehn, J. B. Green, Jr., R. M. Lessler, Dean V. Power, Walter W. Hays, John A. Rau, William L. Parker, P. R. Blankenhorn, D. E. Kline)
Elements of Neutron Interaction Theory(Anthony Foderaro)

A Review of the Italian Activities for the Thermal Recycling of Plutonium

G. Schileo

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 360-366

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT72-A31202

Experimental Investigation of In-Reactor Molten Fuel Performance

C. Lepscky, G. M. Testa, H. Hougaard, K. W. Jones

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 367-395

Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31203

Fluidized Bed Calcination of Radioactive Wastes Using In-Bed Combustion Heating

T. K. Thompson, G. E. Lohse, B. R. Wheeler

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 396-405

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT72-A31204

Dimensional Stability of Tantalum Control Rods in LMFBRs

J. F. Bates, A. L. Pitner

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 406-409

Technical Paper / Material / dx.doi.org/10.13182/NT72-A31205

Fast Reactor Irradiation of Boron Carbide Powder

A. L. Pitner

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 410-417

Technical Paper / Material / dx.doi.org/10.13182/NT72-A31206

A Mathematical Model for the Measurement of Gas Properties with Alpha-Particle Gauges

R. P. Gardner, K. Verghese, J. I. Cehn

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 418-429

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT72-A31207

Reduction of Tritium from Underground Nuclear Explosives

J. B. Green, Jr., R. M. Lessler

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 430-436

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT72-A31208

Ground Motion Prediction Method for Simultaneously Detonated Multiple Underground Nuclear Explosives

Dean V. Power

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 437-443

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT72-A31209

A Review of the Ground Motion Prediction Problem for Plowshare Underground Engineering Applications

Walter W. Hays

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 444-457

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT72-A31210

Measurement of Antiscatter Grid Effectiveness in Thermal-Neutron Radiography of Hydrogenous Materials

John A. Rau, William L. Parker

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 458-461

Technical Paper / Instrument / dx.doi.org/10.13182/NT72-A31211

A Simplified Apparatus for Short-Term Irradiations at 77°K

P. R. Blankenhorn, D. E. Kline

Nuclear Technology / Volume 16 / Number 2 / November 1972 / Pages 462-464

Technical Note / Radioisotope / dx.doi.org/10.13182/NT72-A31212

Number 3

Table of Contents
Authors(Pekka A. O. Jauho, Lasse J. Mattila, E. U. Khan, S. J. Milioti, A. Sherman, R. L. Ritzman, J. A. Gieseke, T. J. Walker, Lee A. James, Jerry F. Kerrisk, David G. Clifton, R. J. Price, D. E. Parks, Nance D. Kunz, John L. Gainer, James L. Kelly, C. L. Schuske, D. C. Hunt, G. W. Keilholtz, R. E. Moore, Milton E. McLain, Jr.)
Unified Theory of Nuclear Models and Forces(Norman Austern)
Applications of Low Energy and Gamma Rays(Frederick D. Seward)
“The Effects of Transverse Flow Through Graphite on Fission Product Movement in HTGR-Type Systems,”(M. N. Özişik, M. D. Silverman)
“The Interrelationship Between Swelling and Irradiation Creep,”(W. G. Wolfer, J. P. Foster, F. A. Garner)