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Volume 73

Number 1

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