NSUF 16-797: In situ studies of radiation damage in nanostructured austenitic stainless steels
Technical Abstract
The main objective of this RTE proposal is to use in situ radiation technique (at IVEM-Argonne National Lab) to interrogate radiation induced microstructure evolution in nanostructured austenitic stainless steels. The ultimate goal is to design nanostructured radiation tolerant materials for advanced nuclear reactors. The system to be investigated include nanocrystalline (NC) austenitic 304L stainless steel (304L SS), and 2) NC 316L SS. Nanocrystalline steels have been prepared via equal channel angular pressing (ECAP). Novelty. Nanostructured metallic materials hold great promise to significantly enhance radiation tolerance of a variety of reactor materials. Previous NEUP studies by the PIs have shown that He ion irradiated NC austenitic Fe-14Cr-16Ni had much lower defect density than coarse grained materials, implying NC materials may significantly reduce void swelling under neutron radiation. However the fundamental mechanisms of enhanced radiation tolerance remain unclear. In situ radiation technique at IVEM – Argonne National Laboratory will allow us to examine the interaction of defect loops with high angle grain boundaries during heavy ion irradiation in NC 304L SS. Major tasks in this project include the 1) investigation of defect-grain boundary interactions and size effect; 2) the influence of radiation dose rate and temperature on defect accumulation; and 3) the radiation stability of nanograins.
Expected period of performance: January-September 2017
Additional Info
| Field | Value |
|---|---|
| Abstract | Technical Abstract The main objective of this RTE proposal is to use in situ radiation technique (at IVEM-Argonne National Lab) to interrogate radiation induced microstructure evolution in nanostructured austenitic stainless steels. The ultimate goal is to design nanostructured radiation tolerant materials for advanced nuclear reactors. The system to be investigated include nanocrystalline (NC) austenitic 304L stainless steel (304L SS), and 2) NC 316L SS. Nanocrystalline steels have been prepared via equal channel angular pressing (ECAP). Novelty. Nanostructured metallic materials hold great promise to significantly enhance radiation tolerance of a variety of reactor materials. Previous NEUP studies by the PIs have shown that He ion irradiated NC austenitic Fe-14Cr-16Ni had much lower defect density than coarse grained materials, implying NC materials may significantly reduce void swelling under neutron radiation. However the fundamental mechanisms of enhanced radiation tolerance remain unclear. In situ radiation technique at IVEM – Argonne National Laboratory will allow us to examine the interaction of defect loops with high angle grain boundaries during heavy ion irradiation in NC 304L SS. Major tasks in this project include the 1) investigation of defect-grain boundary interactions and size effect; 2) the influence of radiation dose rate and temperature on defect accumulation; and 3) the radiation stability of nanograins. Expected period of performance: January-September 2017 |
| Award Announced Date | 2016-12-16T07:45:40.283 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Wei-Ying Chen |
| Irradiation Facility | None |
| PI | Xinghang Zhang |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 797 |