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Volume 57

Number 2

A Liquid-Metal Fast Breeder Reactor Core Design with Seed Blanket Modular Assemblies

Bal Raj Sehgal, Ching-Lu Lin, Edward L. Fuller

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 149-162

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A26277

Dynamic Analysis of the Condensate Feedwater System in Boiling Water Reactor Plants

Junichi Tanji, Takashi Omori

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 163-174

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A26278

Experimental Modeling of Hydrogen Evolution Rates from Surfaces with Exposed Aluminum in Contact with Containment Sprays in Pressurized Water Reactor Nuclear Power Plants

L. E. S. Smith, R. O. Lane, P. V. Guthrie

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 175-178

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A26279

ROSA-III Base Test Series for a Large Break Loss-of-Coolant Accident in a Boiling Water Reactor

K. Tasaka, M. Shiba, Y. Koizumi, Y. Anoda, N. Abe

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 179-191

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A26280

Characteristics and Behavior of Emulsion at Nuclear Fuel Reprocessing

Kozo Gonda, Koichiro Oka, Takeshi Nemoto

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 192-202

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT82-A26281

ELESTRES: A Finite Element Fuel Model for Normal Operating Conditions

Henry H. Wong, Ertugrul Alp, W. R. Clendening,+ M. Tayal,+, Lloyd R. Jones

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 203-212

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26282

Determination of Thermal Accommodation Coefficients of Helium, Argon, and Xenon on a Surface of Zircaloy-2 at About 25°C

Lloyd B. Thomas, Sudarshan K. Loyalka

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 213-219

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26283

A Model for Gap Conductance in Nuclear Fuel Rods

Sudarshan K. Loyalka

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 220-227

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26284

Cost and Other Effects of Reduced Fuel Pellet Diameters

David J. Dixon, Mohamed A. Elmaghrabi, Ian C. Rickard

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 228-233

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26285

Bend Testing for Miniature Disks

Fan Hsiung Huang, Margaret L. Hamilton, Gary L. Wire

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 234-242

Technical Paper / Material / dx.doi.org/10.13182/NT82-A26286

Gamma Treatment of Sewage Sludge with Spent Nuclear Fuel

Norberto Piccinini, Rodolfo Simonetto, Giovanni Del Tin

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 243-254

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT82-A26287

Scaling Laws of Transient Heat and Mass Flow for Modeling the Loss-of-Coolant Accident

S. Benedek

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 255-263

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT82-A26288

Flow Measurement in Sodium and Water Using Pulsed-Neutron Activation: Part 1, Theory

Howard A. Larson, Charles C. Price, Robert N. Curran, John I. Sackett

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 264-271

Technical Paper / Analyse / dx.doi.org/10.13182/NT82-A26289

Flow Measurement in Sodium and Water Using Pulsed-Neutron Activation: Part 2, Experiment

Charles C. Price, Howard A. Larson, Robert N. Curran, John I. Sackett

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 272-284

Technical Paper / Analyse / dx.doi.org/10.13182/NT82-A26290

Application of an Ion Exchange Method for Sensitivity Improvement of an Automated Radionuclide Analysis System

Hiromi Tokoi, Hiroshi Kitaguchi, Masaaki Fujii, Katsuhiro Mizuno, Akira Ishizuka, Toyonori Kudou, Akira Ogushi

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 285-291

Technical Paper / Analyse / dx.doi.org/10.13182/NT82-A26291

Analytical Approximations for the Long-Term Decay Behavior of Spent Fuel and High-Level Waste

Carl M. Malbrain, Richard K. Lester, John M. Deutch

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 292-305

Technical Paper / Education / dx.doi.org/10.13182/NT82-A26292