The chemical state of the fission products in oxide fuels

A review is given on the chemical behaviour of the fission products in steady-state operated nuclear oxide fuels. The evaluation of irradiation experiments results in the description of the release, the transport properties and the alloying and reaction behaviour of the fission products in their dif...

Full description

Saved in:
Bibliographic Details
Published inJournal of nuclear materials Vol. 131; no. 2; pp. 221 - 246
Main Author Kleykamp, H.
Format Journal Article
LanguageEnglish
Published Amsterdam Elsevier B.V 01.01.1985
Elsevier
Subjects
Applied sciences
Energy
Exact sciences and technology
Fuels
Nuclear fuels
Preparation and processing of nuclear fuels
Plutonium IV Uranium IV Oxides Mixed
Fission product
Oxides
Nuclear fuel
West Germany
Cycle
Irradiated nuclear fuel
Uranium IV Oxides
Online AccessGet full text

Cover

More Information
Summary:A review is given on the chemical behaviour of the fission products in steady-state operated nuclear oxide fuels. The evaluation of irradiation experiments results in the description of the release, the transport properties and the alloying and reaction behaviour of the fission products in their different chemical states. Out-of-pile results are presented on the solubility of some fission product oxides in UO 2 and (U, Pu)O 2 and on the phase behaviour of selected multi-component fission product systems. The consequences for the melting point, the thermal conductivity and the shift of the O M -ratio of irradiated oxide fuels are outlined. The paper is complemented by a synopsis of the methods of the elemental analysis on irradiated materials in a micrometer scale.
ISSN:0022-3115
1873-4820
DOI:10.1016/0022-3115(85)90460-X