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
Abstract	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.
Award Announced Date	2020-01-08T00:00:00
Awarded Institution	None
Facility	None
Facility Tech Lead
Irradiation Facility	None
PI	Ramprashad Prabhakaran
PI Email	[email protected]
Project Type	CINR
RTE Number	3074