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Volume 42

Number 3

Critical Separation Between Subcritical Clusters of Low Enriched UO2 Rods in Water with Fixed Neutron Poisons

S. R. Bierman, B. M. Durst, E. D. Clayton

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 237-249

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32178

Intercomparison of Auto- and Cross-Power Spectral Density Surveillance Systems for Sodium Boiling Detection in Fast Reactors

Joachim Ehrhardt

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 250-263

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32179

Characterization of Fragmented Fuel from a Thermal Fuel-Sodium Interaction

S. Gross, D. Vollath

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 264-271

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32180

Hydrogen Transport in a Toroidal Plasma Using Multigroup Discrete-Ordinates Methodology

B. R. Wienke, W. F. Miller, Jr., T. J. Seed

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 272-288

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32181

Loss-of-Coolant Accidents in Small Compact Nuclear Reactors

R. C. Sanders, G. E. Mueller

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 289-296

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT79-A32182

Tracer Techniques for the Input Accountability of Plutonium in Reprocessing Plants: Magtrap and Leadtrap

C. K. Mathews, H. C. Jain, V. D. Kavimandan, S. K. Aggarwal

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 297-303

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT79-A32183

Some Calculations of the Failure Statistics of Coated Fuel Particles

David G. Martin

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 304-311

Technical Paper / Fuel / dx.doi.org/10.13182/NT79-A32184

Tritium Permeation Through Fe-2¼Cr-1 Mo Steam Generator Material

Terrence A. Renner, Donald J. Raue

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 312-319

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32185

Filtration of Sodium-Fire Aerosols

A. Alexas, S. Jordan, W. Lindner

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 320-323

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32186

The Effect of Axial Stress on the Transient Mechanical Response of 20% Cold-Worked Type 316 Stainless-Steel Cladding

H. Yamada

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 324-331

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32187

Calculation of the Influence of the Radial Temperature Gradient on Cladding Dilatation

D. I. R. Norris

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 332-334

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32188

Arguments Concerning the Evaluation of Cladding Dilatation due to Thermodiffusion

H. Venker, M. Bober, G. Schumacher

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Page 335

Department / Letter to the Editor / dx.doi.org/10.13182/NT79-A32189

The Mass Spectrometric Determination of Uranium-235 in Uranium Hexafluoride

W. Beyrich, G. Spannagel

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 337-342

Technical Paper / Analysis / dx.doi.org/10.13182/NT79-A32190

Neutron Fluence Measurements with Solid-State Nuclear Track Detectors: Results of a Comparative Study with Gold and Indium Foils

A. Aframian

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 343-349

Technical Paper / Technique / dx.doi.org/10.13182/NT79-A32191

Bubble Worth Variation in Molten Cores from a Hypothetical Core Disruptive Acident

Charles R. Marotta

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 350-352

Technical Note / Reactor / dx.doi.org/10.13182/NT79-A32192

Radiological Implications of Plutonium Recycle and the use of Thorium Fuels in Thermal Power Reactor Operations

H. F. MacDonald, S. Nair

Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 353-361

Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT79-A32193