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Technical Paper

Possibilities of Using Hypostoichiometric Uranium Dioxide in Thermionic Fuel Elements

929238

08/03/1992

Event
27th Intersociety Energy Conversion Engineering Conference (1992)
Authors
A. S. Gontar Research Institute of Scientific Industrial Association“Lutch”
V. S. Gutnik Research Institute of Scientific Industrial Association“Lutch”
D. Yu. Lubimov Research Institute of Scientific Industrial Association“Lutch”
Yu. V. Nikolaev Research Institute of Scientific Industrial Association“Lutch”
A. S. Panov Research Institute of Scientific Industrial Association“Lutch”
Ye. M. Rakitskaya Research Institute of Scientific Industrial Association“Lutch”
Abstract
Content
Advantages of using UO2-X in fuel elements are discussed.
Change of the initial uranium dioxide content due to burn-up, themal diffusion, as well as fuel component carry-over through the fuel element cladding and vent system is calculated. It is shown that while the fuel element works, the oxygen coefficient increases. The initial value of O/U=1.990-1.998 providing preservation of the hypostoichiometric content during life time is recommended.
The authors results on UO2-X structure investigation under conditions of heating-cooling and long storage, as well as comparative data on free swelling are given besides literature data on UO2-X properties.
Meta Tags
Topics
Oxygen
Affiliated or Co-Author
Research Institute of Scientific Industrial Association“Lutch”
Details
DOI
https://doi.org/10.4271/929238
Pages
6
Citation
Gontar, A., Gutnik, V., Lubimov, D., Nikolaev, Y. et al., "Possibilities of Using Hypostoichiometric Uranium Dioxide in Thermionic Fuel Elements," SAE Technical Paper 929238, 1992, https://doi.org/10.4271/929238.
Additional Details
Publisher
SAE International
Published
Aug 3, 1992
Product Code
929238
Content Type
Technical Paper
Language
English