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

Field	Value
Abstract	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.
Award Announced Date	2018-02-01T14:18:58.573
Awarded Institution	None
Facility	None
Facility Tech Lead	Yong Yang
Irradiation Facility	None
PI	MATTHEW COOK
PI Email	[email protected]
Project Type	RTE
RTE Number	1256