Published June 1992
| Version v1
Journal article
A comparison of the behaviour of fission gases in UO2±x and α-U3O8-z
Creators
- 1. Materials and Chemistry Div., AEA Reactor Services, Harwell Lab. (United Kingdom)
- 2. Davy Faraday Research Lab., Royal Institution of Great Britain, London (United Kingdom)
Description
Atomistic simulation techniques have been used to study the behaviour of fission gas atoms in UO2± x and α-U3O8-2. In this paper, we show how the solution energies and migration mechanisms change as a function of the oxygen content of the fuel. In particular, it is shown that the calculated solution energies decrease from UO2-x to UO2+x but increase again on further oxidation to U3O8. Migration of Xe and Kr in UO2± x proceeds via a tetravacancy trap cluster. In U3O8-z, Xe and Kr movement is assisted by oxygen vacanciesk F120501805larly low activation energies for migration are predicted in the case of radiation-assisted vacancy formation. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 188
- Journal Page Range
- p. 216-221.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- Fall meeting of the European Materials Research Society (E-MRS). Symposium E on nuclear materials for fission reactors.
- Dates
- 5-8 Nov 1991.
- Place
- Strasbourg (France).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 24000446
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION PRODUCTS; MIGRATION; STOICHIOMETRY; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ISOTOPES; MATERIALS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; URANIUM COMPOUNDS