NSUF 18-CINR-14787: High-dose ion irradiation testing and relevant post-irradiation examination of friction-stir-welded ODS MA956 alloy

Since 2011 improved accident tolerant fuels (ATF) and claddings have been a major area of research worldwide, after the loss of coolant accident (LOCA) that took place in Japan. One of the primary goals of the Fuel Cycle R&D program is the development of ATF and cladding materials for light water reactors (LWR), which exhibit increased oxidation resistance during a LOCA. Alternate cladding materials with significantly reduced oxidation kinetics in high-temperature steam environments (when compared to the zirconium alloys) that could reduce heating and hydrogen generation rates, are being investigated. Advanced ferritic (Fe-Cr-Al) alloys are being considered as alternative cladding materials for the current fleet of LWR. The Fe-Cr-Al ferritic alloys are highly resistant to oxidation, due to the formation of an Al2O3-based protective oxide scale at high temperatures. Hence, these advanced alloys may have an advantage over zirconium-based alloys under severe accident conditions.

Additional Info

Field	Value
Awarded Institution	Pacific Northwest National Laboratory
CINR Number	18-14787
Embargo End Date	2028-01-08
NSUF Call	FY 2018 CINR
PI	Ramprashad Prabhakaran
Project Member	Mr. Ramprashad Prabhakaran, Scientist - Pacific Northwest National Laboratory (https://orcid.org/0000-0002-8117-2677)
Project Notes	Awarded on 08/16/2018
Project Type	CINR
RTE Number	3074