American Nuclear Society

Home / Store / Journals / Electronic Articles / Nuclear Technology / Volume 138 / Number 3

ODS Steel Clad MOX Fuel-Pin Fabrication and Irradiation Performance in EBR-II

James Bottcher, Shigeharu Ukai, Masaki Inoue

Nuclear Technology

Volume 138 / Number 3 / June 2002 / Pages 238-245


Member Price:$27.00
Member Savings:$3.00

Oxide dispersion strengthened (ODS) steel cladding on mixed-oxide fuel pins offers high-temperature strength and creep rupture resistance properties for a long-life fast reactor. The fabrication and irradiation of the large diameter ODS steel cladding with high-density mixed-oxide pellets were performed at the Argonne National Laboratory Experimental Breeder Reactor II. Two developmental ODS alloys and two fuel-pin designs were used in this study. The tests were continually monitored during irradiation followed by nondestructive and destructive examinations. Both designs were successful and demonstrated the potential of ODS steel as a cladding material.

Questions or comments about the site? Contact the ANS Webmaster.