NSUF 19-1773: BET and TEM characterization of nuclear graphite irradiated at temperatures below 230°C
Graphite is the moderator material of some Generation IV reactors concepts and British Advanced Gas-cooled Reactors (AGR). Failure of multiple graphite components is considered to be one of the limiting factors for plant life of the AGR and some Generation IV designs. Part of the assessment performance predictions of Generation IV graphite bricks are based on simulations that require information of the volumetric lattice changes in single graphite crystals. TEM data at temperatures below 300˚C is currently unavailable limiting the understanding of graphitic material defects at the conditions that may be found in carbon-based materials in Generation IV reactors designs. The authors propose to implement Brunauer-Emmett-Teller (BET) and Transmission Electron Microscopy (TEM) analysis to determine the effects of irradiation under low temperature conditions. The study of samples irradiated at low temperatures would also improve the fundamental understanding of the defect mobility and evolution in the graphite.
Additional Info
| Field | Value |
|---|---|
| Abstract | Graphite is the moderator material of some Generation IV reactors concepts and British Advanced Gas-cooled Reactors (AGR). Failure of multiple graphite components is considered to be one of the limiting factors for plant life of the AGR and some Generation IV designs. Part of the assessment performance predictions of Generation IV graphite bricks are based on simulations that require information of the volumetric lattice changes in single graphite crystals. TEM data at temperatures below 300˚C is currently unavailable limiting the understanding of graphitic material defects at the conditions that may be found in carbon-based materials in Generation IV reactors designs. The authors propose to implement Brunauer-Emmett-Teller (BET) and Transmission Electron Microscopy (TEM) analysis to determine the effects of irradiation under low temperature conditions. The study of samples irradiated at low temperatures would also improve the fundamental understanding of the defect mobility and evolution in the graphite. |
| Award Announced Date | 2019-05-14T16:25:08.15 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kory Linton |
| Irradiation Facility | None |
| PI | Wenjing Li |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 1773 |