NSUF 18-1256: Fission Product Distribution Comparison in Irradiated and Safety Tested AGR-1 and AGR-2 TRISO Fuel Particles

TRISO-coated fuel is an important piece of developing new generation reactors. The changes that TRISO fuel undergoes during potential accident temperatures is unknown and is a roadblock in licensing, modeling, and understanding the effects of different manufacturing processes. This proposal is planned to examine already prepared TEM lamellae to establish the difference in fission product distribution within two differently manufactured TRISO particles. Both samples were taken from kernels irradiated to burnup of up to 18.6 FIMA and then safety tested at 1600?C, one TRISO particle was manufactured using a lab coating and the other using an industrially coated particle. These particles are different than others studied due to the fact that they were annealed after irradiation which could cause several effects such as, chemical stratification, void swelling, cracking, or other high temperature effects. By comparing the two distributions of fission products the reliability of fission product retention and evolution can be determined. This will provide information for qualifying TRISO fuels along with giving data to improve the fuel fabrication process.

Additional Info

Mező	Érték
Awarded Institution	University of Florida
Embargo End Date	2026-02-27
Facility Tech Lead	Yong Yang
NSUF Call	FY 2018 RTE 1st Call
PI	MATTHEW COOK
Project Member	Yong Yang, Associate Professor - University of Florida (https://orcid.org/0000-0002-0247-6219)
Project Member	Dr. Isabella van Rooyen, Senior Technical Advisor Advanced Material Systems - Pacific Northwest National Laboratory (https://orcid.org/0000-0001-8524-938X)
Project Member	MATTHEW COOK - University of Florida
Project Notes	Awarded on 12/13/2017
Project Type	RTE
RTE Number	1256