NSUF 16-640: TEM investigation of the SiC containment layer of irradiated nuclear fuel particles

We propose to study the interaction of fission products with the barrier SiC layer of TRISO nuclear fuel particles. This study will utilize electron microscopy and energy dispersive x-ray spectroscopy to gather images and elemental identification maps to provide insight as to the behavior and pathway mechanisms of fission products through the SiC matrix. The research objectives are to provide knowledge on the reaction mechanisms of metallic fission products in the SiC containment layer under varying simulated accident conditions in order to understand the cause of metallic fission product release and potential particle failure. This information will allow for the contribution to and re-evaluation of current particle design in order to maximize safety and to certify particles for use in next generation nuclear reactors.

Additional Info

Field	Value
Abstract	We propose to study the interaction of fission products with the barrier SiC layer of TRISO nuclear fuel particles. This study will utilize electron microscopy and energy dispersive x-ray spectroscopy to gather images and elemental identification maps to provide insight as to the behavior and pathway mechanisms of fission products through the SiC matrix. The research objectives are to provide knowledge on the reaction mechanisms of metallic fission products in the SiC containment layer under varying simulated accident conditions in order to understand the cause of metallic fission product release and potential particle failure. This information will allow for the contribution to and re-evaluation of current particle design in order to maximize safety and to certify particles for use in next generation nuclear reactors.
Award Announced Date	2016-04-11T00:00:00
Awarded Institution	None
Facility	None
Facility Tech Lead	Kory Linton
Irradiation Facility	None
PI	Jeff Terry
PI Email	[email protected]
Project Type	RTE
RTE Number	640