Kernel Migration for HTGR Fuels from the System Th‐U‐Pu‐C‐O‐N
- 1 January 1977
- journal article
- Published by Wiley in Journal of the American Ceramic Society
- Vol. 60 (1-2), 5-14
- https://doi.org/10.1111/j.1151-2916.1977.tb16082.x
Abstract
No abstract availableKeywords
This publication has 20 references indexed in Scilit:
- Irradiation performance of HTGR fuel rods in HFIR experiment HRB-6Published by Office of Scientific and Technical Information (OSTI) ,1975
- Kernel Migration in Coated Carbide Fuel ParticlesNuclear Technology, 1975
- Thermodynamics and phase relationships of the ternary lanthanum-uranium-oxygen systemJournal of Solid State Chemistry, 1974
- Unterdrückung des amoebeneffektes bei beschichteten brennstoffteilchen mit carbidkern für hochtemperaturreaktorenJournal of Nuclear Materials, 1973
- Carbon Thermal Diffusion in the UC2-C SystemJournal of the American Ceramic Society, 1972
- Thermodynamic data for U-Ce-oxidesJournal of Inorganic and Nuclear Chemistry, 1970
- Les diagrammes de phases U-UN-UO2 et UO2-UN-N2Journal of Nuclear Materials, 1970
- Thermal diffusion in closed oxide fuel systemsJournal of Nuclear Materials, 1969
- Oxygen and uranium diffusion in uranium dioxide (a review)Journal of Nuclear Materials, 1969
- Equilibrium Oxygen Pressures Over Solid Solutions of Urania‐Yttria and Urania‐Lanthana at 1100° to 14OO°CJournal of the American Ceramic Society, 1967