PERFORMANCE OF HT9 CLAD METALLIC FUEL AT HIGH-TEMPERATURE

Authors
PAHL RG LAHM CE HAYES SL
Citation
Rg. Pahl et al., PERFORMANCE OF HT9 CLAD METALLIC FUEL AT HIGH-TEMPERATURE, Journal of nuclear materials, 204, 1993, pp. 141-147
Citations number
3
Categorie Soggetti
Nuclear Sciences & Tecnology","Metallurgy & Mining","Material Science
Journal title
Journal of nuclear materials → ACNP
ISSN journal
00223115
Volume
204
Year of publication
1993
Pages
141 - 147
Database
ISI
SICI code
0022-3115(1993)204:<141:POHCMF>2.0.ZU;2-1
Abstract
Irradiation testing and post-irradiation examination of HT9 clad U-10Z r metallic fuel has been carried out in the EBR-II reactor. Peak cladd ing temperatures in the range of 630 to 660-degrees-C were obtained in order to study high temperature breach behavior of metallic fuel. Of the 15 experimental fuel elements tested to 10 at% burnup, two breache d by stress rupture. Breach behavior was found to be totally benign fo r reactor operations. Significant fuel/cladding chemical interactions involving lanthanide-series fission products and carbide depletion wer e observed in the hottest cladding region.