NSUF 18-1542: Microstructural investigation of hydride reorientation in zirconium based spent nuclear fuel cladding
The objective of this project is to investigate the influences of irradiation and the fundamental mechanism of hydride reorientation in spent nuclear fuel cladding. Though the impacts of high temperature and high-pressure conditions on hydride reorientation have been investigated for many nonirradiated Zr cladding alloys, a data gap remains regarding potential synergistic effects of irradiation at these conditions in spent nuclear fuel rods. To more realistically investigate the mechanism and influences of hydride reorientation behavior, spent nuclear fuel rods from H.B. Robinson, North Anna, and Surry-2 U.S. commercial nuclear power reactors have been exposed to hydride reorientation treatments. This project requires advanced characterization techniques including focused ion beam (FIB), transmission electron microscopy (TEM), Scanning Transmission Electron Microscopy (S/TEM), and Electron Energy Loss Spectroscopy (EELS). FIB will be used to perform the final sample thinning for TEM analysis. The TEM will be utilized to produce detailed images of the dislocation loops surrounding the hydrides. Precipitate size, distribution, and dissolution determined using S/TEM and EELS will be compared for the three irradiated cladding conditions before and after hydride reorientation treatments. Data collected will provide key insight into the fundamental mechanism of hydride reorientation in spent nuclear fuel clad specimens that have been exposed to commercial light water reactor conditions. This will directly address issue of degradation in nuclear fuel cladding in the United States during the transportation and post-irradiation storage of nuclear fuel. The Nuclear Regulatory Commission (NRC) regulations on the storage of used nuclear fuel are spelled out in 10 Code of Federal Regulations (CFR) Part 72, in which the licensing of dry storage is being proposed to increase from 20 years to 40 years, and beyond. In this case, understanding the effects of hydrides and hydride reorientation in nuclear fuel cladding (potential embrittlement mechanisms) become increasingly important to formulate the technical basis for continued safe, long-term storage of used nuclear fuel that will accommodate the final used fuel management options. This project is predicted to take no more than 5 months to complete. Fabrication of TEM samples using FIB techniques is expected to take no more than 1 month. Data collection from TEM, S/TEM, and EELS techniques is expected to take no more than 3 months. Data analysis and reporting will take approximately 4 months from the date of initial data collection.
추가 정보
| 필드 | 값 |
|---|---|
| Abstract | The objective of this project is to investigate the influences of irradiation and the fundamental mechanism of hydride reorientation in spent nuclear fuel cladding. Though the impacts of high temperature and high-pressure conditions on hydride reorientation have been investigated for many nonirradiated Zr cladding alloys, a data gap remains regarding potential synergistic effects of irradiation at these conditions in spent nuclear fuel rods. To more realistically investigate the mechanism and influences of hydride reorientation behavior, spent nuclear fuel rods from H.B. Robinson, North Anna, and Surry-2 U.S. commercial nuclear power reactors have been exposed to hydride reorientation treatments. This project requires advanced characterization techniques including focused ion beam (FIB), transmission electron microscopy (TEM), Scanning Transmission Electron Microscopy (S/TEM), and Electron Energy Loss Spectroscopy (EELS). FIB will be used to perform the final sample thinning for TEM analysis. The TEM will be utilized to produce detailed images of the dislocation loops surrounding the hydrides. Precipitate size, distribution, and dissolution determined using S/TEM and EELS will be compared for the three irradiated cladding conditions before and after hydride reorientation treatments. Data collected will provide key insight into the fundamental mechanism of hydride reorientation in spent nuclear fuel clad specimens that have been exposed to commercial light water reactor conditions. This will directly address issue of degradation in nuclear fuel cladding in the United States during the transportation and post-irradiation storage of nuclear fuel. The Nuclear Regulatory Commission (NRC) regulations on the storage of used nuclear fuel are spelled out in 10 Code of Federal Regulations (CFR) Part 72, in which the licensing of dry storage is being proposed to increase from 20 years to 40 years, and beyond. In this case, understanding the effects of hydrides and hydride reorientation in nuclear fuel cladding (potential embrittlement mechanisms) become increasingly important to formulate the technical basis for continued safe, long-term storage of used nuclear fuel that will accommodate the final used fuel management options. This project is predicted to take no more than 5 months to complete. Fabrication of TEM samples using FIB techniques is expected to take no more than 1 month. Data collection from TEM, S/TEM, and EELS techniques is expected to take no more than 3 months. Data analysis and reporting will take approximately 4 months from the date of initial data collection. |
| Award Announced Date | 2018-09-17T12:03:14.55 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kory Linton |
| Irradiation Facility | None |
| PI | Tyler Smith |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 1542 |