Published June 1992 | Version v1
Journal article

A comparison of the behaviour of fission gases in UO2±x and α-U3O8-z

  • 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