NSUF 16-CINR-10764: Radiation-Enhanced Diffusion of Ag, Ag-Pd, Eu, and Sr in Neutron Irradiated PyC/SiC Diffusion Couples
The objective of the study is to investigate thermal diffusion and neutron radiation enhanced diffusion of fission product species in SiC; providing fundamental insight into the release of fission product is in TRISO fuel. This will be accomplished through diffusion couple analysis and neutron irradiations of diffusion couples which have layer microstructure and interface attributes nearly identical to those found in TRISO fuel particles from the AGR 2 irradiation campaign, which represent fuel particles that might be generated by commercial-scale equipment. The AGR 2 layer properties serve as a baseline diffusion couple test material, while other designs with tailored SiC microstructures and PyC/SiC interfacial stitching will explore variables influencing fission product interfacial interactions and transport. The investigation of diffusion in systems representative of TRISO fuel will provide accurate, high-quality data on the diffusion kinetics of fission products in the SiC layer under conditions representative of TRISO fuel operation, which is needed to validate and provide input for fuel performance models. To the author’s knowledge this would represent the first systematic study of the influence of neutron irradiation on diffusion in SiC.
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of the study is to investigate thermal diffusion and neutron radiation enhanced diffusion of fission product species in SiC; providing fundamental insight into the release of fission product is in TRISO fuel. This will be accomplished through diffusion couple analysis and neutron irradiations of diffusion couples which have layer microstructure and interface attributes nearly identical to those found in TRISO fuel particles from the AGR 2 irradiation campaign, which represent fuel particles that might be generated by commercial-scale equipment. The AGR 2 layer properties serve as a baseline diffusion couple test material, while other designs with tailored SiC microstructures and PyC/SiC interfacial stitching will explore variables influencing fission product interfacial interactions and transport. The investigation of diffusion in systems representative of TRISO fuel will provide accurate, high-quality data on the diffusion kinetics of fission products in the SiC layer under conditions representative of TRISO fuel operation, which is needed to validate and provide input for fuel performance models. To the author’s knowledge this would represent the first systematic study of the influence of neutron irradiation on diffusion in SiC. |
| Award Announced Date | 2016-06-14T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | |
| Irradiation Facility | None |
| PI | Tyler Gerczak |
| PI Email | [email protected] |
| Project Type | CINR |
| RTE Number | 3042 |