NSUF 13-425: Microstructure Analysis of HIgh Dose Neutron Irradiated Microstructures
The objective of this project is to characterize the microstructure of alloys irradiated in the BOR-60 reactor to doses of 20 and 40 dpa to compare with ion irradiations designed to emulate the reactor irradiation. This is part of a larger objective of establishing ion irradiation as a major tool for developing radiation-resistant materials for current light water reactors and for advanced reactor concepts. Ion irradiation has the potential for solving the problem of extremely long lead times for reactor irradiations, the high cost of reactor irradiations and the lack of test reactors to conduct irradiations. The overall program has as its goal, an understanding of the evolution of the irradiated microstructure, which can then be used to tailor ion irradiations to achieve optimum emulation of the reactor irradiated microstructure for the specific neutron spectrum. Characterization will focus on the key features of the irradiated microstructure, including dislocation lines and loops, radiation induced segregation at grain boundaries, radiation-induced precipitates or solute clusters and the void size distribution. Methods employed will be TEM/STEM/EFTEM and APT on samples prepared using FIB lift out from 3 mm TEM discs of thickness 250 micrometers. Expected period of performance is from November 2014 to March 2017. If successful, the characterization conducted at ATR-NSUF will be a critical element in helping to establish the conditions under which ion irradiation must be conducted to emulate the microstructure of alloys irradiated in reactor. The impact of this achievement will be to provide a way to assess the radiation tolerance of alloys in time frames and with budgets that are orders of magnitude shorter than for reactor irradiation programs.
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of this project is to characterize the microstructure of alloys irradiated in the BOR-60 reactor to doses of 20 and 40 dpa to compare with ion irradiations designed to emulate the reactor irradiation. This is part of a larger objective of establishing ion irradiation as a major tool for developing radiation-resistant materials for current light water reactors and for advanced reactor concepts. Ion irradiation has the potential for solving the problem of extremely long lead times for reactor irradiations, the high cost of reactor irradiations and the lack of test reactors to conduct irradiations. The overall program has as its goal, an understanding of the evolution of the irradiated microstructure, which can then be used to tailor ion irradiations to achieve optimum emulation of the reactor irradiated microstructure for the specific neutron spectrum. Characterization will focus on the key features of the irradiated microstructure, including dislocation lines and loops, radiation induced segregation at grain boundaries, radiation-induced precipitates or solute clusters and the void size distribution. Methods employed will be TEM/STEM/EFTEM and APT on samples prepared using FIB lift out from 3 mm TEM discs of thickness 250 micrometers. Expected period of performance is from November 2014 to March 2017. If successful, the characterization conducted at ATR-NSUF will be a critical element in helping to establish the conditions under which ion irradiation must be conducted to emulate the microstructure of alloys irradiated in reactor. The impact of this achievement will be to provide a way to assess the radiation tolerance of alloys in time frames and with budgets that are orders of magnitude shorter than for reactor irradiation programs. |
| Award Announced Date | 2013-06-13T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Yaqiao Wu |
| Irradiation Facility | None |
| PI | Gary Was |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 425 |