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Volume 30

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Number 1

Uranium-233 Breeding and Neutron Multiplying Blankets for Fusion Reactors

Andrew G. Cook, James A. Maniscalco

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 5-11

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31618

On the Use and Influence of Gamma Radiation in Reactor Noise Measurements

Bruno Bärs

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 12-23

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31619

The Development of an Environmental Monitoring System for the Continuous Detection of Low-Level Radioactive Gases

R. H. Jabs, W. A. Jester

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 24-32

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT76-A31620

Technological Development Concerning the Gas-Cooled Fast Breeder Reactor Test Bundle for the Irradiation Test in the Helium Loop at Mol

M. Peehs, P. Rau

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 33-46

Technical Paper / Fuel / dx.doi.org/10.13182/NT76-A31621

Procedure for Determining Leachabilities of Radioactive Waste Forms

J. A. Kelley, R. M. Wallace

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 47-51

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT76-A31622

Interrelationships Between Creep Life Criteria for Four Nuclear Structural Materials

M. K. Booker, V. K. Sikka

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 52-64

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31623

Radiative Heat Transfer in Molten UO2 Based on the Rosseland Diffusion Method

Edward E. Anderson

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 65-70

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31624

A Simple Method for Calculations of Steady-State Creep Rates in Nonconservative Plastic Deformation

G. L. Wire, J. L. Straalsund

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 71-76

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31625

Instrumented Fast-Reactor Irradiation of Boron Carbide Pellets

A. L. Pitner

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 77-85

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31626

Volume Reduction of Plutonium-Contaminated Soil

J. H. Horton, E. L. Albenesius

Nuclear Technology / Volume 30 / Number 1 / July 1976 / Pages 86-88

Technical Note / Radioactive Waste / dx.doi.org/10.13182/NT76-A31627

Number 2

History of Fissile Array Measurements in the United States

C. L. Schuske, Hugh C. Paxton

Nuclear Technology / Volume 30 / Number 2 / August 1976 / Pages 101-137

Technical Paper / Criticality Array Data and Calculational Method / Chemical Processing / dx.doi.org/10.13182/NT76-A31612

A Review of Criticality Safety Models Used in Evaluating Arrays of Fissile Materials

Douglas C. Hunt

Nuclear Technology / Volume 30 / Number 2 / August 1976 / Pages 138-165

Technical Paper / Criticality Array Data and Calculational Method / Chemical Processing / dx.doi.org/10.13182/NT76-A31613

The Monte Carlo Method for Array Criticality Calculations

Deanne Dickinson, G. Elliott Whitesides

Nuclear Technology / Volume 30 / Number 2 / August 1976 / Pages 166-189

Technical Paper / Criticality Array Data and Calculational Method / Chemical Processing / dx.doi.org/10.13182/NT76-A31614

Comparative Calculational Evaluation of Array Criticality Models

Douglas C. Hunt, Deanne Dickinson

Nuclear Technology / Volume 30 / Number 2 / August 1976 / Pages 190-214

Technical Paper / Criticality Array Data and Calculational Method / Chemical Processing / dx.doi.org/10.13182/NT76-A31615

Number 3

Uranium Resources—Are they Adequate?

Robert D. Nininger

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 224-231

Technical Paper / Uranium Resource / Fuel Cycle / dx.doi.org/10.13182/NT76-A31638

U3O8 Supply in Technical and Commercial Transition

P. F. Schutt, J. S. Hobbs

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 232-236

Technical Paper / Uranium Resource / Fuel Cycle / dx.doi.org/10.13182/NT76-A31639

The Changing Scene for Uranium in Canada

Noel O’Brien

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 237-241

Technical Paper / Uranium Resource / Fuel Cycle / dx.doi.org/10.13182/NT76-A31640

Uranium: The Market and Adequacy of Supply

Bernard H. Cherry

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 242-245

Technical Paper / Uranium Resource / Fuel Cycle / dx.doi.org/10.13182/NT76-A31641

Transient Hydraulics and Heat Transfer in Turbulent Flow

Hiroshi Kawamura

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 246-255

Technical Paper / Uranium Resource / Reactor / dx.doi.org/10.13182/NT76-A31642

Safety Advantages of Prestressed Concrete Reactor Vessels

Zdeněk P. Bažant

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 256-260

Technical Paper / Uranium Resource / Reactor / dx.doi.org/10.13182/NT76-A31643

A Tokamak Experimental Power Reactor

W. M. Stacey, Jr., V. A. Maroni, J. R. Purcell, M. A. Abdou, P. J. Bertoncini, J. N. Brooks, J. B. Darby, Jr., K. Evans, Jr., J. A. Fasolo, R. L. Kustom, J. S. Moenich, J. S. Patten, D. L. Smith, H. C. Stevens, S. T. Wang

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 261-298

Technical Paper / Uranium Resource / Reactor / dx.doi.org/10.13182/NT76-A31644

Theoretical and Experimental Dynamic Analysis of the H. B. Robinson Nuclear Plant

T. W. Kerlin, E.M. Katz, J. G. Thakkar, J. E. Strange

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 299-316

Technical Paper / Uranium Resource / Reactor / dx.doi.org/10.13182/NT76-A31645

Removal of Radioiodine from Gas Streams by Electrolytic Scrubbing

J. C. Mailen, D. E. Horner

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 317-324

Technical Paper / Uranium Resource / Chemical Processing / dx.doi.org/10.13182/NT76-A31646

Use of Chemical Equilibrium Data to Calculate Iodox Column Operations

J. C. Mailen

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 325-332

Technical Paper / Uranium Resource / Chemical Processing / dx.doi.org/10.13182/NT76-A31647

Velocity Measurements in the Subchannel of the Wire-Spaced Subassembly

Toshihide Ohtake, Shinichi Uruwashi, Keiichi Takahashi

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 333-349

Technical Paper / Uranium Resource / Fuel / dx.doi.org/10.13182/NT76-A31648

Neutron Spectrum and Radial Power Distribution Measurements in a TRIGA Reactor Fuel Element

Walter L. Weaver III, Marvin E. Wyman, Barclay G. Jones

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 350-360

Technical Paper / Uranium Resource / Fuel / dx.doi.org/10.13182/NT76-A31649

Cladding Ovalities in Advanced Liquid-Metal Fast Breeder Reactor Fuel Elements

Jerry F. Kerrisk, John O. Barner, Roy L. Petty

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 361-375

Technical Paper / Uranium Resource / Fuel / dx.doi.org/10.13182/NT76-A31650

Swelling and Microstructural Changes in Irradiated Vanadium Alloys

J. Bentley, F. W. Wiffen

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 376-384

Technical Paper / Uranium Resource / Material / dx.doi.org/10.13182/NT76-A31651

Grain Boundary Penetration Kinetics of Nitrided Type 304L Stainless Steel

J. A. Reeves, Jr., D. L. Olson, W. L. Bradley

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 385-389

Technical Paper / Uranium Resource / Material / dx.doi.org/10.13182/NT76-A31652

Influence of Section Thickness on Fatigue Crack Growth in Type 304 Stainless Steel

Paul Shahinian

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 390-397

Technical Paper / Uranium Resource / Material / dx.doi.org/10.13182/NT76-A31653

Fast-Neutron Hodoscope at TREAT: Data Processing, Analysis, and Results

A. De Volpi, R. R. Stewart, J. P. Regis, G. S. Stanford, E. A. Rhodes

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 398-421

Technical Paper / Uranium Resource / Instrument / dx.doi.org/10.13182/NT76-A31654

Evaluation of Initial Loading Counting Rate Data from Experiments with the Mock-Up Core for the Fast Flux Test Facility

J. T. Mihalczo, G. C. Tillett, D. L. Selby

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 422-433

Technical Paper / Uranium Resource / Instrument / dx.doi.org/10.13182/NT76-A31655

Neutron Downscattering in Laser-Induced Fusioning Plasmas

Finis H. Southworth, Hugh D. Campbell

Nuclear Technology / Volume 30 / Number 3 / September 1976 / Pages 434-436

Technical Note / Uranium Resource / Reactor / dx.doi.org/10.13182/NT76-A31656