NSUF 19-1670: A study of the tensile response of HT-9 alloys following ATR irradiation to doses between 0.01 and 10 dpa at 300, 450 and 550C
The objective of this program is to investigate the tensile properties of HT-9 following neutron irradiation in the Advanced Test Reactor (ATR) to target doses between 0.01 dpa to 10 dpa at target temperatures of 300, 450 and 550C. These are the highest neutron dose alloys for this alloy heat currently available. This particular heat is the same one which was irradiated in the last Phénix experiments to much higher doses, however, those specimens are still not available. Nevertheless, this work will provide a lower-dose foundation for interpreting the higher dose results once they become available. This work is also complementary to the DOE-NE ART SNAP (High Dose Radiation Effects Project – lead by LANL/U Michigan) where HT-9 is being irradiated to very high doses in Russia and compared to high dose irradiations at U Michigan. The tensile properties determined here will fill in lower dose effects of irradiation on the tensile properties of this alloy which are needed to support the understanding of the early development of damage in this irradiation resistant alloy. The temperature range of our irradiated specimens also covers a range which should explore maxium hardening at lower temperatures and less damage at the higher temperatures where recovery is possible. The temperature range also brackets the likely low end to high end of actual application of this alloy in advanced reactor service conditions.
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of this program is to investigate the tensile properties of HT-9 following neutron irradiation in the Advanced Test Reactor (ATR) to target doses between 0.01 dpa to 10 dpa at target temperatures of 300, 450 and 550C. These are the highest neutron dose alloys for this alloy heat currently available. This particular heat is the same one which was irradiated in the last Phénix experiments to much higher doses, however, those specimens are still not available. Nevertheless, this work will provide a lower-dose foundation for interpreting the higher dose results once they become available. This work is also complementary to the DOE-NE ART SNAP (High Dose Radiation Effects Project – lead by LANL/U Michigan) where HT-9 is being irradiated to very high doses in Russia and compared to high dose irradiations at U Michigan. The tensile properties determined here will fill in lower dose effects of irradiation on the tensile properties of this alloy which are needed to support the understanding of the early development of damage in this irradiation resistant alloy. The temperature range of our irradiated specimens also covers a range which should explore maxium hardening at lower temperatures and less damage at the higher temperatures where recovery is possible. The temperature range also brackets the likely low end to high end of actual application of this alloy in advanced reactor service conditions. |
| Award Announced Date | 2019-02-08T00:00:00 |
| Awarded Institution | Center for Advanced Energy Studies |
| Facility | Microscopy and Characterization Suite |
| Facility Tech Lead | Tarik Saleh, Yaqiao Wu |
| Irradiation Facility | None |
| PI | Huan Yan |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 1670 |