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Influence of the Diluent on the Radiolytic Degradation of TBP in TBP, 30% (v/v)-Diluent- HNO3 Systems
-
A. V. BELLIDO
und M. N. RUBENICH
Veröffentlicht/Copyright:
1. Februar 1984
Published Online: 1984-2-1
Published in Print: 1984-2-1
© 2013 Oldenbourg Wissenschaftsverlag GmbH, Rosenheimer Str. 145, 81671 München
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Artikel in diesem Heft
- Masthead
- PREFACE
- Chemistty of the Purex Process
- Advances in Chemistry of the Actinide Elements
- Characterisation of Dissolution Residues — Fuel Element Cladding and Fission Product Insolubles
- Basic Aspects of the Get-Precipitation Route to Nuclear Fuel
- U-Pu Recovery by Molten Alkaline Sulphates
- Plutonium Conversion by the Gel-Supported Precipitation (GSP) Process at the ENEA-EUREX Reprocessing Plant
- Plutonium Recovery from Combustible Wastes Treated by Incineration and Pyrolysis
- Contamination of Metal Surfaces with Plutonium from Aqueous Solutions
- Influence of the Diluent on the Radiolytic Degradation of TBP in TBP, 30% (v/v)-Diluent- HNO3 Systems
- Trioxane Initiated Formic Acid Denitration of Plutonium-Bearing Acid Solution
- Application of Inorganic Ion Exchangers Prepared by Gel Supported Precipitation to Radwaste Ceramics
- Nuclear Fuel Conversion and Fabrication Chemistry
- Actinide Separation from MAW Process Streams via Ion-Exchange Techniques
- INSTRUCTIONS TO CONTRIBUTORS
Artikel in diesem Heft
- Masthead
- PREFACE
- Chemistty of the Purex Process
- Advances in Chemistry of the Actinide Elements
- Characterisation of Dissolution Residues — Fuel Element Cladding and Fission Product Insolubles
- Basic Aspects of the Get-Precipitation Route to Nuclear Fuel
- U-Pu Recovery by Molten Alkaline Sulphates
- Plutonium Conversion by the Gel-Supported Precipitation (GSP) Process at the ENEA-EUREX Reprocessing Plant
- Plutonium Recovery from Combustible Wastes Treated by Incineration and Pyrolysis
- Contamination of Metal Surfaces with Plutonium from Aqueous Solutions
- Influence of the Diluent on the Radiolytic Degradation of TBP in TBP, 30% (v/v)-Diluent- HNO3 Systems
- Trioxane Initiated Formic Acid Denitration of Plutonium-Bearing Acid Solution
- Application of Inorganic Ion Exchangers Prepared by Gel Supported Precipitation to Radwaste Ceramics
- Nuclear Fuel Conversion and Fabrication Chemistry
- Actinide Separation from MAW Process Streams via Ion-Exchange Techniques
- INSTRUCTIONS TO CONTRIBUTORS