Possibilities of Using Hypostoichiometric Uranium Dioxide in Thermionic Fuel Elements Research Institute of Scientific Industrial Association"Lutch"

Format:

Conference/Event

Author/Creator:

Gontar, A. S., author.

Conference Name:

27th Intersociety Energy Conversion Engineering Conference (1992) (1992-08-03 : San Diego, California, United States)

Language:

English

Physical Description:

1 online resource

Place of Publication:

Warrendale, PA SAE International 1992

Summary:

AbstractAdvantages 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

Notes:

Vendor supplied data

Publisher Number:

929238

Access Restriction:

Restricted for use by site license