THE RELEASE OF FISSION-PRODUCTS FROM DEGRADED UO2 FUEL - THERMOCHEMICAL ASPECTS

Authors
CORDFUNKE EHP KONINGS RJM
Citation
Ehp. Cordfunke et Rjm. Konings, THE RELEASE OF FISSION-PRODUCTS FROM DEGRADED UO2 FUEL - THERMOCHEMICAL ASPECTS, Journal of nuclear materials, 201, 1993, pp. 57-69
Citations number
72
Categorie Soggetti
Nuclear Sciences & Tecnology","Metallurgy & Mining","Material Science
Journal title
Journal of nuclear materials → ACNP
ISSN journal
00223115
Volume
201
Year of publication
1993
Pages
57 - 69
Database
ISI
SICI code
0022-3115(1993)201:<57:TROFFD>2.0.ZU;2-V
Abstract
This review describes the chemical aspects of the release of the impor tant fission products. Their behaviour in the fuel, in the reactor coo lant system (primary system), and during core-concrete interactions, i s discussed. Special attention is given to thermochemical modeling to incorporate the results of recent studies on the acquisition of thermo chemical data for relevant species by experimental and evaluation tech niques.