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Number 1

Table of Contents
Authors (G. Apostolakis, T. L Chu, J. A. Figg, N. J. McCormick, R. E. Schenter, F. Schmittroth, Robert E. Einziger, Bobby R. Seidel, Chong Chiu, Neil E. Todreas, Warren M. Rohsenow, Vladimír Balek, Miroslav Vobořil, Václav Baran, Jungchung Jung, J. Gilbert, R. Marfaing, H. Vidal, Sümer Şahin, Jacques Ligou, Donald D. Lanning, Bruce O. Barnes, W. A. Scheffler)
Comments on “Thermal-Neutron Flux Depression in Cylindrical UO2 Fuel Rods” (Raymond P. Sullivan)
Reply to “Comments on Thermal-Neutron Flux Depression in Cylindrical UO2 Fuel Rods" (James E. Gibson, J. N. Anno)
Further Comments on “Thermal-Neutron Flux Depression in Cylindrical UO2 Fuel Rods” (Raymond P. Sullivan)
Proceedings of the Atoms for Peace Award, 1957–1969 (D. A. Bromley)
Energy Conversion Engineering (Alfred Schneider)
Photochemistry of Small Molecules (G. K. Vemulapalli)
Engineering for Nuclear Fuel Reprocessing (J. A. Buckham)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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)
Flow Visualization (Clifford J. Cremers)
Positronium and Muonium Chemistry (L. B. Church)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT80-A32533

Volume 50

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