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Number 1

Table of Contents
Authors (Sadao Hattori, Der-Jhy Shieh, Belle R. Upadhyaya, J. C. Courtney, K. R. Ferguson, J. P. Bacca, Thomas J. Downar, Young Jin Kim, Frederick R. Best, Michael J. Driscoll, Larned B. Asprey, Scott A. Kinkead, P. Gary Eller, Brent J. Lewis, Colin R. Phillips, M. J. F. Notley, Chaitanyamoy Ganguly, Hans Langen, Erich Zimmer, Erich R. Merz, Victor R. Deitz, W. J. Mills, Bernard Mastel, Tatsuhiko Uda, Hajime Iba, Hiroyuki Tsuchiya, Tetsuya Miyake, Kunihiko Takeda, Hatsuki Onitsuka, Toshinori Watanabe)
Comments on “Thermodynamical Calculations on the Behavior of Gaseous Iodine Species Following a Hypothetical Severe Light Water Reactor Accident” (Masaaki Uchida)
Antimony Telluride Formation Hypothesized from Reactor Coolant System Sample Data (V. F. Baston, K. J. Hofstetter)
Geological Disposal of Radioactive Waste In Situ Experiments in Granite (Jaak J. K. Daemen)
Quantum Electrodynamics of Strong Fields (Howard R. Reiss)
Low Reynolds Number Flow Heat Exchangers (Thomas R. Rehm)
High Pressure Measurement Techniques (Thomas R. Rehm)
Nuclear Engineering Data Bases, Standards and Numerical Analysis (Walter Loewenstein)

A Logical Selection of Measures for Quality Assurance on the Integrity of Liquid-Metal Fast Breeder Reactor Primary Boundaries
Sadao Hattori
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 7-18
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16197
Stochastic Estimation Approach for the Evaluation of Thermal-Hydraulic Parameters in Pressurized Water Reactors
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 19-29
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16198
Radiological Safety Analysis of the Hot Fuel Examination Facility/South
J. C. Courtney, K. R. Ferguson, J. P. Bacca
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 30-41
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16199
A Reverse Depletion Method for Pressurized Water Reactor Core Reload Design
Thomas J. Downar, Young Jin Kim
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 42-54
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A16200
Prospects for the Recovery of Uranium from Seawater
Frederick R. Best, Michael J. Driscoll
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 55-68
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A16201
Low-Temperature Conversion of Uranium Oxides to Uranium Hexafluoride Using Dioxygen Difluoride
Larned B. Asprey, Scott A. Kinkead, P. Gary Eller
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 69-71
Technical Paper | Chemical Processing | doi.org/10.13182/NT86-A16202
A Model for the Release of Radioactive Krypton, Xenon, and Iodine from Defective UO₂ Fuel Elements
Brent J. Lewis, Colin R. Phillips, M. J. F. Notley
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 72-83
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16203
Sol-Gel Microsphere Pelletization Process for Fabrication of High-Density ThO₂—2% UO₂ Fuel for Advanced Pressurized Heavy Water Reactors
Chaitanyamoy Ganguly, Hans Langen, Erich Zimmer, Erich R. Merz
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 84-95
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16204
Residual Depth Profile in the Evaluation of Granular Adsorbents
Victor R. Deitz
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 96-101
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A16205
Deformation and Fracture Characteristics for Irradiated Inconel X-750
W. J. Mills, Bernard Mastel
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 102-108
Technical Paper | Material | doi.org/10.13182/NT86-A16206
Decontamination of Uranium-Contaminated Mild Steel by Melt Refining
Tatsuhiko Uda, Hajime Iba, Hiroyuki Tsuchiya
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 109-115
Technical Paper | Material | doi.org/10.13182/NT86-A16207
Analysis of Enrichment Factor of Uranium Enrichment by Redox Chromatography
Tetsuya Miyake, Kunihiko Takeda, Hatsuki Onitsuka, Toshinori Watanabe
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 116-123
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT86-A16208

Number 2

Table of Contents
Authors (Aaron Barkatt, Barbara C. Gibson, Pedro B. Macedo, Charles J. Montrose, William Sousanpour, Alisa Barkatt, Morad-Ali Boroomand, Victor Rogers, Miguel Penafiel, M. J. Apted, G. L. McVay, J. W. Wald, Aaron Barkatt, Pedro B. Macedo, Barbara C. Gibson, Charles J. Montrose, Larry L. Hench, Pedro B. Macedo, Aaron Barkatt, Barbara C. Gibson, Charles J. Montrose, Yigal Ronen, Yaakov Fahima, Kiyomi Funabashi, Tetsuo Fukasawa, Fumio Kawamura, Hideo Yusa, Makoto Kikuchi, Noriharu Sasaki, Toshio Yamadera, Reiner Papp, Herbert Loser, John D. Rogers, Alexander Sesonske, Ken Amano, Masayoshi Ishida)
Preface: Performance of Borosilicate Glass High-Level Waste Forms in Disposal Systems (Edward J. Hennelly)
Symmetries in Nuclear Structure (N. V. V. J. Swamy)
Perturbation Methods in Heat Transfer (B. D. Ganapol)
Advances in Two-Phase Flow and Heat Transfer, Vols. 1 and 2 (R. K. Chohan, Belle R. Upadhyaya)
Before It's Too Late (Hugh F. Henry)
The Search for Charm, Beauty, and Truth at High Energies (Hugh F. Henry)

Mechanisms of Defense Waste Glass Dissolution
Aaron Barkatt, Barbara C. Gibson, Pedro B. Macedo, Charles J. Montrose, William Sousanpour, Alisa Barkatt, Morad-Ali Boroomand, Victor Rogers, Miguel Penafiel
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 140-164
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33780
Release of Actinides from Defense Waste Glass Under Simulated Repository Conditions
M. J. Apted, G. L. McVay, J. W. Wald
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 165-178
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33781
Modeling of Waste Form Performance and System Release
Aaron Barkatt, Pedro B. Macedo, Barbara C. Gibson, Charles J. Montrose
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 179-187
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33782
International Collaboration in Nuclear Waste Solidification
Larry L. Hench
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 188-198
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33783
Long-Term Release Rates of Borosilicate Glass Waste Forms
Pedro B. Macedo, Aaron Barkatt, Barbara C. Gibson, Charles J. Montrose
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 199-209
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33784
Analysis of High Convertor Pressure Tube Reactors
Yigal Ronen, Yaakov Fahima
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 210-219
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Fission Reactor | doi.org/10.13182/NT86-A33785
Reuse System for Powdered Ion-Exchange Resins
Kiyomi Funabashi, Tetsuo Fukasawa, Fumio Kawamura, Hideo Yusa, Makoto Kikuchi, Noriharu Sasaki, Toshio Yamadera
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 220-227
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33786
Fuel Reprocessing Versus Direct Disposal of Spent Fuel—A Comparison from the Standpoint of Radiological Safety
Reiner Papp, Herbert Loser
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 228-235
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33787
Analysis of Graphite-Hydrogen-Methane Kinetics Above 1600 K
John D. Rogers, Alexander Sesonske
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 236-242
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Material | doi.org/10.13182/NT86-A33788
Application of the Vortex Method to Analysis of Coolant Temperature Fluctuation
Ken Amano, Masayoshi Ishida
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 243-251
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Heat Transfer and Fluid Flow | doi.org/10.13182/NT86-A33789

Number 3

Table of Contents
Authors (Kenny C. Gross, B. R. Seidel, Sabyasachi Chakraborty, Bruno Covelli, Peter Michael Herttrich, Wu-Hung Peng, Rakesh Chawla, Rudolf Seiler, Kurt Gmür, Yasuo Koizumi, Hiroshige Kumamaru, Yutaka Kukita, Masahiro Kawaji, Masahiro Osakabe, Richard R. Schultz, Mitsugu Tanaka, Kanji Tasaka, J. C. Helton, R. L. Iman, J. D. Johnson, C. D. Leigh, Alex Galperin, S. M. Ho, K. C. Radford, Kazuaki Yanagisawa, Sang Woon Shin, Hee Cheon No, Hisayoshi Mitamura, Takashi Murakami, Tsunetaka Banba, Takayuki Amaya)
Models and Parameters for Environmental Radiological Assessment (Anton Bayer)
The Unity of the Fundamental Interactions (Paul F. Zweifel)
Radionuclide Distribution and Transport in Terrestrial and Aquatic Ecosystems (Gerald A. Schlapper)

Statistical Analysis of Duplex-Tube Performance in Experimental Breeder Reactor II Superheater SU-712
Kenny C. Gross, B. R. Seidel
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 263-277
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16070
A Concept of a Small Controlled, Filtered Venting System and an Add-On Decay Heat Removal System to Mitigate the Consequences of Core-Melt Accidents
Sabyasachi Chakraborty, Bruno Covelli, Peter Michael Herttrich
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 278-285
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16071
Skyshine Radiation from a Pressurized Water Reactor Containment Dome
Wu-Hung Peng
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 286-295
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16072
Effects of Fuel Enrichment on the Physics Characteristics of Plutonium-Fueled Light Water High Converter Reactors
Rakesh Chawla, Rudolf Seiler, Kurt Gmür
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 296-305
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16073
Blind-Blind Prediction by RELAP5/MOD1 for a 0.1% Very Small Cold-Leg Break Experiment at ROSA-IV Large-Scale Test Facility
Yasuo Koizumi, Hiroshige Kumamaru, Yutaka Kukita, Masahiro Kawaji, Masahiro Osakabe, Richard R. Schultz,* Mitsugu Tanaka, Kanji Tasaka
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 306-319
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16074
Uncertainty and Sensitivity Analysis of a Model for Multicomponent Aerosol Dynamics
J. C. Helton,* R. L. Iman, J. D. Johnson,+, C. D. Leigh
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 320-342
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16075
Feasibility of the Once-Through Thorium Fuel Cycle for CANDU Reactors
Alex Galperin
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 343-349
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A16076
Structural Chemistry of Solid Solutions in the UO₂-Gd₂O₃ System
S. M. Ho, K. C. Radford
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 350-360
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16077
An Evaluation of the Influence of Fuel Design Parameters and Burnup on Pellet/Cladding Interaction for Boiling Water Reactor Fuel Rod Through In-Core Diameter Measurement
Kazuaki Yanagisawa
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 361-377
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16078
Effect of Heat Flux on the Concentration Factor in Crevices of Nuclear Steam Generators
Sang Woon Shin, Hee Cheon No
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 378-383
Technical Paper | Material | doi.org/10.13182/NT86-A16079
Small Calciner for Drying and Calcination of SYNROC Slurry
Hisayoshi Mitamura, Takashi Murakami, Tsunetaka Banba, Takayuki Amaya
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 384-388
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT86-A16080

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