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Volume 26

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Number 1

  • Table of Contents
  • Authors(Charles T. Rombough, Billy V. Koen, G. LaVergne, J. E. Robinson, J. G. Martel, S. J. Altschuler, C. L. Schuske, Walter A. Stark, Jr., Lee A. James, T. H. Smith, J. Greenborg, W. T. Matheson, Donald E. Burton, Charles M. Snell, Jon E. Bryan, I. Y. Borg, Paul J. Rose, Alan M. Jacobs, Edward S. Kenney, C. L. Aseltine, R. A. Strich, R. W. Hardie, W. W. Little, R. P. Omberg)
  • Peaceful Nuclear Explosions III(John A. Wethington, Jr.)

Total Energy Investment in Nuclear Power Plants

Charles T. Rombough, Billy V. Koen

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 5-11

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24399

On the Matching of Fusion Breeders to Heavy-Water Reactors

G. LaVergne, J. E. Robinson, J. G. Martel

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 12-22

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24400

Fissile-Solution Storage in Pipes Isolated by Concrete or Water

S. J. Altschuler, C. L. Schuske

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 23-34

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24401

Diffusion Analyses for Systems of Spherical Particles

Walter A. Stark, Jr.

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 35-45

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24402

Fatigue-Crack Propagation in a Cast Stainless Steel

Lee A. James

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 46-53

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24403

Benefit/Risk Analysis of Cardiac Pacemakers Powered by Betacel® Promethium-147 Batteries

T. H. Smith, J. Greenborg, W. E. Matheson

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 54-64

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24404

Computer Design of High-Explosive Experiments to Simulate Subsurface Nuclear Detonations

Donald E. Burton, Charles M. Snell, Jon B. Bryan

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 65-87

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT75-A24405

Radioactivity Trapped in Melt Produced by a Nuclear Explosion

I. Y. Borg

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 88-100

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT75-A24406

Dynamic Nondestructive Inspection Using Thermal Neutrons

Paul J. Rose, Alan M. Jacobs, Edward S. Kenney

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 101-106

Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24407

Time-Resolved Neutron Radiography Using a Fast Pulse Reactor

C. L. Aseltine, R. A. Strich

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 107-114

Technical Paper / Technique / dx.doi.org/10.13182/NT75-A24408

A Comprehensive Expression for the Doubling Time of Fast Breeder Reactors

R. W. Hardie, W. W. Little, R. P. Omberg

Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 115-116

Technical Note / Reactor / dx.doi.org/10.13182/NT75-A24409

Number 2

  • Table of Contents
  • Authors(Robert W. Conn, Gerald L. Kulcinski, Halil Avci, Mohamed El-Maghrabi, P. M. Haas, C. A. Erdman, P. L. Garner, A. B. Reynolds, A. B. Reynolds, C. A. Erdman, M. Kirbiyik, M. Bober, H. Kleykamp, G. Schumacher, N. C. Cole, G. M. Slaughter, M. R. Louthan, Jr., J. A. Donovan, G. R. Caskey, Jr., P. Barthelemy, R. Berger, R. Boucher, L. Hayet, Shizuo Yamashita, Tsuyoshi Okamoto, J. A. Cooper, H. L. Nielson, N. A. Wogman, R. W. Perkins, K. D. Feintuch, J. L. Meem, M. Bober, H. U. Karow, K. Schretzmann)

New Concepts for Controlled Fusion Reactor Blanket Design

Robert W. Conn, Gerald L. Kulcinski, Halil Avci, Mohamed El-Maghrabi

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 125-145

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24413

Noncoherence and Two-Phase Heat Transfer in LMFBR Fuel-Coolant Interaction

P. M. Haas, C. A. Erdman, P. L. Garner, A. B. Reynolds

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 146-164

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24414

Fuel Vapor Generation in LMFBR Core Disruptive Accidents

A. B. Reynolds, C. A. Erdman, M. Kirbiyik

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 165-171

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A24415

Investigation of Radial Plutonium Redistribution in Mixed Oxide Fuels Irradiated in a Fast Flux

M. Bober, H. Kleykamp, G. Schumacher

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 172-182

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24416

Development of Brazing Filler Metals for Molybdenum

N. C. Cole, G. M. Slaughter

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 183-191

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24417

Tritium Absorption in Type 304L Stainless Steel

M. R. Louthan, Jr., J. A. Donovan, G. R. Caskey, Jr.

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 192-200

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24418

The Development of Californium-252 Sealed Sources at the Commissariat a l’Energie Atomique

P. Barthelemy, R. Berger, R. Boucher, L. Hayet

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 201-214

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24419

Effect of Separation Factors on Product Assay of an Ideal Cascade Composed of UF6 Centrifuges

Shizuo Yamashita, Tsuyoshi Okamoto

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 215-223

Technical Paper / Isotopes Separation / dx.doi.org/10.13182/NT75-A24420

Feasibility Study of In Situ Sediment Analysis by X-Ray Fluorescence

J. A. Cooper, H. L. Nielson, N. A. Wogman, R. W. Perkins

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 224-231

Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24421

Fabrication of Thin Uranium Dioxide Films for Neutron Flux Measurements

K. D. Feintuch, J. L. Meem

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 232-236

Technical Note / Instrument / dx.doi.org/10.13182/NT75-A24422

Vapor Pressure Measurements of Oxide Fuel Between 3000 and 5000 K Using Laser Heating

M. Bober, H. U. Karow, K. Schretzmann

Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 237-241

Technical Note / Technique / dx.doi.org/10.13182/NT75-A24423

Number 3

Simplified Small-Break Blowdown Models

L. W. Ward

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 247-253

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24426

Rocky Flats Experience with Borosilicate Glass Rings for Criticality Control

C. L. Schuske, J. D. McCarthy

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 254-264

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24427

Nominally Reflected Pipe Intersections Containing Fissile Solution

Deanne Dickinson

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 265-277

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24428

Swelling of Uranium Silicide Fuel During Postirradiation Heating

R. B. Matthews, M. L. Swanson

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 278-286

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24429

The Relationship Between Rupture Life and Creep Properties of Cr —1 Mo Steel

R. L. Klueh

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 287-296

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24430

Effect of Fast Reactor Fluence on Postirradiation Rupture of Type 316 Stainless Steel

A. J. Lovell

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 297-306

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24431

A Plutonium-238-Fueled Cardiac Pacemaker

Michel Alais, Rene Berger, Rene Boucher, Kenneth A. Gasper, Paul Laurens

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 307-319

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24432

Monte Carlo Dosimetry Calculation for Boron Neutron-Capture Therapy in the Treatment of Brain Tumors

Owen Leslie Deutsch, Brian Winston Murray

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 320-339

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24433

Remote Sensing of Plutonium by the Low-Energy Scattered Flux

A. E. Profio, G. C. Huth

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 340-351

Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24434

Critical Experiments—Benchmarks (Pu-U Systems)

S. R. Bierman

Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 352-381

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT75-A24435

Number 4

  • Table of Contents
  • Authors(R. W. Conn, T. Y. Sung, M. A. Abdou, Mohamed A. Abdou, Layton J. Wittenberg, Charles W. Maynard, W. R. McDonell, E. F. Sturcken, H. Kwast, J. A. Vitti, P. K. Doherty, G. F. Di Lauro, J. C. Gilbertson, D. W. Stuteville, E. R. Siegmann, J. C. Gilbertson, R. C. Noyes, P. K. Doherty, S. A. Caspersson, N. Hanus, D. W. Stuteville, C. A. Strand, R. E. Schenter, A. Sy Ong, E. E. Teixeira, R. K. Nair, W. Chubb, A. C. Hott, B. M. Argall, G. R. Kilp, J. Locante, W. M. Lowder, B. A. Engholm, W. E. Kreger, J. J. Sapyta, G. L. Simmons)

Comparative Study of Radioactivity and Afterheat in Several Fusion Reactor Blanket Designs

R. W. Conn, T. Y. Sung, M. A. Abdou

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 391-399

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24440

A Fusion Design Study of Nonmobile Blankets with Low Lithium and Tritium Inventories

Mohamed A. Abdou, Layton J. Wittenberg, Charles W. Maynard

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 400-419

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24441

Development of High-Performance Uranium-Metal Fuels for Savannah River Reactors

W. R. McDonell, E. F. Sturcken

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 420-429

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24442

Effect of a Loss of Flow on a Single LMFBR-Type Fuel Pin

H. Kwast

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 430-441

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24443

Design of Prototype Carbide Subassemblies and an Evaluation of Proof-Testing Plans in the FFTF

J. A. Vitti, P. K. Doherty, G. F. di Lauro, J. C. Gilbertson, D. W. Stuteville

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 442-451

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24444

Safety Margins for Sodium-Bonded Carbide Fuel

E. R. Siegmann, J. C. Gilbertson

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 452-459

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24445

Optimum Pin Diameter for LMFBR Carbide Fuels

R. C. Noyes, P. K. Doherty, S. A. Caspersson, N. Hanus, D. W. Stuteville

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 460-471

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24446

Design and Manufacture of Gas Tags for FFTF Fuel and Control Assemblies

C. A. Strand, R. E. Schenter

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 472-479

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24447

Diffusion of Linearly Distributed Material in an Evaporating Slab

A. Sy Ong, E. E. Teixeira, R. K. Nair

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 480-485

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24448

The Influence of Fuel Microstructure on In-Pile Densification

W. Chubb, A. C. Hott, B. M. Argall, G. R. Kilp

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 486-495

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24449

Panel Discussion: Engineering Problems in Power Reactor Shielding

J. Locante, W. M. Lowder, B. A. Engholm, W. E. Kreger

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 496-507

Technical Paper / Shielding / dx.doi.org/10.13182/NT75-A24450

Shielding Design and Analysis Methods for Pressurized Water Reactors

J. J. Sapyta, G. L. Simmons

Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 508-515

Technical Paper / Shielding / dx.doi.org/10.13182/NT75-A24451