Used Fuel Drying by Vacuum and Forced Gas Circulation for Dry Cask Storage

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 2 of 2
1. Verfasser: Perry, Jonathan E. (VerfasserIn)
Weitere Verfasser: Farouk, Tanvir (VerfasserIn), Khan, Jamil (VerfasserIn), Tulenko, James S. (VerfasserIn), Niemoller, Arthur (VerfasserIn), Knight, Travis W. (VerfasserIn)
Pages:2019
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
Development of Acid Leaching Method to Retrieve High-Level Wastes from Nuclear Waste Glass 2020 Takao, Koichiro
Long Core Life Design Options for the Westinghouse LFR 2020 Kim, T. K.
High-Efficiency Dehalogenation of LiCI-KCI Based Electrorefiner Salt Using Protonated Ultrastable Y-Type (USHY) Zeolite via lon-EXchange 2020 Wasnik, M. S.
Study on Airborne Release Fraction in Hydrogen Explosion by Comparison Between Overpressurization and Hydrogen Explosion 2020 Tamauchi, Yoshikazu
Tritium Detection by Electrochemical Assisted Radiometrics (TRIBECA) 2020 Berhane, Ghebrehiwot
Life Extension and Accelerated Testing 2020 Fluss, Michael J.
Prospective Nuclear Fuel Cycle Characteristics of Advanced Nuclear Energy Systems 2020 Kim, T. K.
Using a Technology and Systems Readiness Assessment to Roadmap a Nuclear Energy R&D Program 2020 Dixon, B. W.
IAEA On-Going Activities on Power Reactors Fuel Engineering and Spent Fuel Management 2020 González-Espartero, Amparo
Characterization of HONTA/SiO2-P Adsorbent for MA(IITLn(III) Separation Flow-Sheet 2020 Takeuchi, Masayuki
Back Extraction Method for Minor Actinide Solvent Extraction Using Solubility-Enhanced Nitrogen-Donor Ligand 2020 Watanabe, Daisuke
Deep Isolation: Innovative Technology for the Disposal of Spent Nuclear Fuel and Other High-Level Waste 2020 Baltzer, Rodney A.
A2-D Correlation to Evaluate Fuel-Cladding Gap Thermal Conductance in Mixed Oxide Fuel Elements for Sodium-Cooled Fast Reactors 2020 Lavarenne, J.
Safety Analysis of the Molten Salt Fast Reactor Fuel Composition Using Moltres 2020 Park, Sun Myung
Successful Integration: Bringing Together the High Burnup Spent Fuel Demonstration Project Team 2020 McEntire, J. A.
System-Wide Impacts of Resolution Options for a Nonconforming Dry Storage System 2020 Chatzidakis, Stylianos
Microfluidic-Based Separation and In-Situ Detection of Selenium(IV) Ion in Radioactive Wastes 2020 Brandt, Aileen
Characterization of Ruthenium Tetroxide Capture from Dry Gas Streams by Silica Gel and Metal Surfaces 2020 Spencer, Barry B.
Porous Glass Approach for Reduction of Secondary Molybdate Phase in Vitrification of PUREX Raffinate 2020 Uruga, Kazuyoshi
Alteration and Leaching Behavior of Simulated Nuclear Waste Glass in Different Acidic Solutions 2020 Kubo, Mayuu
Alle Artikel auflisten