FUEL CLADDING COMPATIBILITY IN U-19PU-10ZR HT9-CLAD FUEL AT ELEVATED-TEMPERATURES/

Authors
COHEN AB TSAI H NEIMARK LA
Citation
Ab. Cohen et al., FUEL CLADDING COMPATIBILITY IN U-19PU-10ZR HT9-CLAD FUEL AT ELEVATED-TEMPERATURES/, Journal of nuclear materials, 204, 1993, pp. 244-251
Citations number
4
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
244 - 251
Database
ISI
SICI code
0022-3115(1993)204:<244:FCCIUH>2.0.ZU;2-G
Abstract
Twenty-five elevated-temperature tests were conducted on irradiated U- 19wt%Pu-10wt%Zr fuel clad with HT9 at the Alpha-Gamma Hot Cell Facilit y at Argonne National Laboratory, Illinois. Samples with burnups as hi gh as 11 at% were tested, and the cladding penetration rates all fall within the data band previously defined. Highlights of the test result s are presented, as are discussions of the cladding penetration mechan ism found in elevated-temperature testing of irradiated metallic fuels .