Literature review of thermal and radiation performance parameters for high-temperature, uranium dioxide fueled cermet materials
- Author
- HAERTLING, C1 ; HANRAHAN, R. J1
[1] Los Alamos National Laboratory, P. O. Box 1663, Los Alamos, NM 87545, United States - Conference title
- Space reactor fuels and materials: Proceedings of the Symposium on Space Reactor Fuels and Materials held in conjunction with the 2006 Annual Meeting of the Minerals, Metals, and Materials Society (TMS), San Antonio, TX, USA, 13 March 2006
- Conference name
- 2006 Annual Meeting of the Minerals, Metals, and Materials Society (TMS). Symposium on Space Reactor Fuels and Materials (TMS). Symposium on Space Reactor Fuels and Materials (San Antonio, TX 2006-03-13)
- Author (monograph)
- SENOR, David (Editor)1 ; WIRTH, Brian (Editor)2 ; HANRAHAN, Robert (Editor)3 ; ZINKLE, Steve (Editor)4 ; UZ, Mehmet (Editor)5 ; OHRINER, Evan (Editor)4 ; COCKERAM, Brian (Editor)6
Minerals, Metals and Materials Society (TMS), Refractory Metals and Materials Committee, Warrendale, PA, United States (Organiser of meeting)
TMS/AMS, Joint Nuclear Materials Committee, United States (Organiser of meeting)
[1] Pacific Northwest National Laboratory, 902 Battelle Boulevard, Richland, WA 99352, United States
[2] University of California, Berkeley, CA, United States
[3] Los Alamos National Laboratory, Los Alamos, NM, United States
[4] Oak Ridge National Laboratory, Oak Ridge, TN, United States
[5] Lafayette College, Easton, PA, United States
[6] Bechtel-Bettis, West Mifflin, PA, United States - Source
Journal of nuclear materials. 2007, Vol 366, Num 3, pp 317-335, 19 p ; ref : 26 ref
- CODEN
- JNUMAM
- ISSN
- 0022-3115
- Scientific domain
- Energy; Metallurgy, welding
- Publisher
- Elsevier, Amsterdam
- Publication country
- Netherlands
- Document type
- Conference Paper
- Language
- English
- Keyword (fr)
- Alliage Application spatiale Article synthèse Cermet Coefficient diffusion Combustible nucléaire Dégradation Haute température Intégrité combustible Performance Uranium dioxyde
- Keyword (en)
- Alloys Space application Review Cermet Diffusion coefficient Nuclear fuel Degradation High temperature Fuel integrity Performance Uranium dioxide
- Keyword (es)
- Aleación Aplicación espacial Artículo síntesis Cermetal Coeficiente difusión Combustible nuclear Degradación Alta temperatura Rendimiento
- Classification
- Pascal
- 001 Exact sciences and technology / 001D Applied sciences / 001D06 Energy / 001D06B Fuels / 001D06B04 Nuclear fuels / 001D06B04C Preparation and processing of nuclear fuels
- Discipline
- Energy
- Origin
- Inist-CNRS
- Database
- PASCAL
- INIST identifier
- 18921847
Sauf mention contraire ci-dessus, le contenu de cette notice bibliographique peut être utilisé dans le cadre d’une licence CC BY 4.0 Inist-CNRS / Unless otherwise stated above, the content of this bibliographic record may be used under a CC BY 4.0 licence by Inist-CNRS / A menos que se haya señalado antes, el contenido de este registro bibliográfico puede ser utilizado al amparo de una licencia CC BY 4.0 Inist-CNRS
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DOI
10.1016/j.jnucmat.2007.03.024 
https://dx.doi.org/10.1016/j.jnucmat.2007.03.024
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