Home / Publications / Journals / Nuclear Technology / Volume 73

Volume 73

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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)
Perturbation Methods in Heat Transfer(B. D. Ganapol)
Symmetries in Nuclear Structure(N. V. V. J. Swamy)
Advances in Two-Phase Flow and Heat Transfer, Vols. 1 and 2(R. K. Chohan, Belle R. Upadhyaya)
The Search for Charm, Beauty, and Truth at High Energies(Hugh F. Henry)
Before It's Too Late(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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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)
The Unity of the Fundamental Interactions(Paul F. Zweifel)
Models and Parameters for Environmental Radiological Assessment(Anton Bayer)
Radionuclide Distribution and Transport in Terrestrial and Aquatic Ecosystems(Gerald A. Schlapper)