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Volume 50

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Number 1

The Unavailability of Systems Under Periodic Test and Maintenance

G. Apostolakis, T. L. Chu

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 5-15

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A17065

Gas Tag Identification of Failed Reactor Assemblies—IV. Analysis Methods

J. A. Figg, N. J. McCormick, R. E. Schenter, F. Schmittroth

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 16-24

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-3

Irradiation Performance of Metallic Driver Fuel in Experimental Breeder Reactor II to High Burnup

Robert E. Einziger, Bobby R. Seidel

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 25-39

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A17067

Turbulent Flow Split Model and Supporting Experiments for Wire-Wrapped Core Assemblies

Chong Chiu, Neil E. Todreas, Warren M. Rohsenow

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 40-52

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A17068

Emanation Thermal Analysis—Results from Characterizing Intermediate Steps and Intermediate Products for Urania Spheres

Vladimír Balek, Miroslav Vobořil, Václav Baran

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 53-59

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A17069

A Comparative Study of Tritium Breeding Performance of Lithium, Li2O, and Li7Pb2 Blankets in a Tokamak Power Reactor

Jungchung Jung

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 60-82

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A17070

Suivi de Rupture de Gaine du Combustible Caramel: Experience CARINE

J. Gilbert, R. Marfaing, H. Vidal

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 83-87

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A17071

The Effect of the Spontaneous Fission of Plutonium-240 on the Energy Release in a Nuclear Explosive

Sümer Şahin, Jacques Ligou

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 88-94

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT80-A17072

Use of Fuel Thermocouple Transient Response for Data Verification and Fuel Rod Modeling

Donald D. Lanning, Bruce O. Barnes, W. A. Scheffler

Nuclear Technology / Volume 50 / Number 1 / August 1980 / Pages 95-107

Technical Paper / Technique / dx.doi.org/10.13182/NT80-A17073

Number 2

  • Table of Contents
  • Authors(F. S. Felber, J. Nagashima, D. G. Andrews, Edward Lantz, J. C. Manaranche, D. Mangin, L. Maubert, G. Colomb, G. Poullot, A. J. Francis, C. R. Iden, B. J. Nine, C. K. Chang, R. Bullough, M. H. Wood, Kenkichi Ishigure, Norihiko Fujita, Takaaki Tamura, Keichi Oshima, Maomi Seko, Tetsuya Miyake, Kohji Inada, Kunihiko Takeda, E. Smith)
  • Positronium and Muonium Chemistry(L. B. Church)
  • Flow Visualization(Clifford J. Cremers)

Fueling Moving Ring Field-Reversed Mirror Reactor Plasmas

F. S. Felber

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 119-123

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32537

An Application of Information Divergence to Nuclear Reactor Noise Analysis

J. Nagashima, D. G. Andrews

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 124-135

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32538

Inherent Safety in the Design of Future Nuclear Plants

Edward Lantz

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 136-147

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32539

Dissolution and Storage Experiment with 4.75-wt%-235U-Enriched UO2 Rods

J. C. Manaranche, D. Mangin, L. Maubert, G. Colomb, G. Poullot

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 148-157

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT80-A32540

Characterization of Organics in Leachates from Low-Level Radioactive Waste Disposal Sites

A. J. Francis, C. R. Iden, B. J. Nine, C. K. Chang

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 158-163

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT80-A32541

Numerical Calculations of the Effect of Recombination on Sink Strengths in the Rate Theory of Void Swelling, Irradiation Creep, and Growth

R. Bullough, M. H. Wood

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 164-168

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32542

Effect of Gamma Radiation on the Release of Corrosion Products from Carbon Steel and Stainless Steel in High Temperature Water

Kenkichi Ishigure, Norihiko Fujita, Takaaki Tamura, Keichi Oshima

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 169-177

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32543

Uranium Isotope Enrichment by Chemical Method

Maomi Seko, Tetsuya Miyake, Kohji Inada, Kunihiko Takeda

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 178-186

Technical Paper / Isotopes Separation / dx.doi.org/10.13182/NT80-A32544

An Appraisal of the Effect of Graphite Interlayers on the Tolerance of Water Reactor Fuel Rods to Power Ramp Defects

E. Smith

Nuclear Technology / Volume 50 / Number 2 / September 1980 / Pages 187-189

Technical Note / Fuel / dx.doi.org/10.13182/NT80-A32545

Number 3

  • Table of Contents
  • Authors(S. K. Bhattacharyya, J. A. Morman, R. G. Bucher, D. M. Smith, W. R. Robinson, E. F. Bennett, A. Kenigsberg, D. Hasan, E. Elias, Richard Simms, Robert K. Lo, William F. Murphy, Alan B. Rothman, George S. Stanford, Carolyn D. Heising-Goodman, John F. Carew, David J. Diamond, Richard Simms, M. Schad, R. Farhadieh, W. H. Gunther, B. H. Erkkila, R. S. Marshall)
  • The Energy Source Book(L. B. Church)

The Effect of Accidental Steam Entry on Gas-Cooled Fast Reactor Integral Neutronics Parameters

S. K. Bhattacharyya, J. A. Morman, R. G. Bucher, D. M. Smith, W. R. Robinson, E. F. Bennett

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 197-218

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32524

Parametric Study of Radioactive Release from a Breached Containment

A. Kenigsberg, D. Hasan, E. Elias

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 219-224

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32525

TREAT Test E8 Simulating a Liquid-Metal Fast Breeder Reactor $3/s Overpower Accident with Irradiated Fast Test Reactor Type Fuel

Richard Simms, Robert K. LO, William F. Murphy, Alan B. Rothman, George S. Stanford

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 225-241

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32526

An Evaluation of the Plutonium Denaturing Concept as an Effective Safeguards Method

Carolyn D. Heising-Goodman

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 242-251

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT80-A32527

Using Fuel Performance to Determine Operating Limit Uncertainty Allowance

John F. Carew, David J. Diamond

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 252-256

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32528

An Evaluation of Fuel Motion in Recent TREAT Experiments with Liquid-Metal Fast Breeder Reactor Fuel

Richard Simms

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 257-266

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32529

To the Corrosion of Austenitic Steel in Sodium Loops

M. Schad

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 267-288

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32530

Application of a Sodium Austenitic Corrosion Model to a Fuel Rod

M. Schad

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 289-297

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32531

One-Dimensional Penetration of Molten UO2 into Substrate Limestone Concrete

R. Farhadieh, W. H. Gunther

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 298-306

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32532

A Thermal Neutron Coincidence Counting System

B. H. Erkkila, R. S. Marshall

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 307-313

Technical Paper / Instrument / dx.doi.org/10.13182/NT80-A32533