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Aqueous Chemical Processes for the Preparation of High Temperature Reactor Fuel Kernels
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E. ZIMMER
Published/Copyright:
August 1, 1978
Published Online: 1978-8-1
Published in Print: 1978-8-1
© 2013 Oldenbourg Wissenschaftsverlag GmbH, Rosenheimer Str. 145, 81671 München
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Articles in the same Issue
- Masthead
- INTRODUCTION
- The Chemistry of Uranium Milling
- Conversion of Uranium Trioxide to Uranium Hexafluoride
- The Chemistry of Plutonium in Sol-Gel Processes
- Chemical Aspects of Mixed Oxide Fuel Production
- The Preparation of HTGR Fissile Fuel Kernels by Uranium-Loading of Ion Exchange Resins
- Aqueous Chemical Processes for the Preparation of High Temperature Reactor Fuel Kernels
- A Review of the Solvent Extraction Process Chemistry of Fission Products
- Pyrochemical Processing of LWR and L M F B R Fuels by the Salt Transport Method
- Use of Electrochemical Processes in Aqueous Reprocessing of Nuclear Fuels
- The Chemistry of Protactinium, Neptunium, Americium, and Curium in the Nuclear Fuel Cycle
- Photo and Radiation Chemistry in Nuclear Fuel Reprocessin
- Glass as a Material for the Final Disposal of Fission Products
- Relevance of the Studies of the OKLO Natural Nuclear Reactors to the Storage of Radioactive Wastes
- Masthead 2
- TABLE OF CONTENTS OF VOLUME 25 (1978)
Articles in the same Issue
- Masthead
- INTRODUCTION
- The Chemistry of Uranium Milling
- Conversion of Uranium Trioxide to Uranium Hexafluoride
- The Chemistry of Plutonium in Sol-Gel Processes
- Chemical Aspects of Mixed Oxide Fuel Production
- The Preparation of HTGR Fissile Fuel Kernels by Uranium-Loading of Ion Exchange Resins
- Aqueous Chemical Processes for the Preparation of High Temperature Reactor Fuel Kernels
- A Review of the Solvent Extraction Process Chemistry of Fission Products
- Pyrochemical Processing of LWR and L M F B R Fuels by the Salt Transport Method
- Use of Electrochemical Processes in Aqueous Reprocessing of Nuclear Fuels
- The Chemistry of Protactinium, Neptunium, Americium, and Curium in the Nuclear Fuel Cycle
- Photo and Radiation Chemistry in Nuclear Fuel Reprocessin
- Glass as a Material for the Final Disposal of Fission Products
- Relevance of the Studies of the OKLO Natural Nuclear Reactors to the Storage of Radioactive Wastes
- Masthead 2
- TABLE OF CONTENTS OF VOLUME 25 (1978)