NSUF 18-1394: Radiation Damage in High Entropy Alloys
Methods: We have investigated various composition of FCC and BCC HEAs using thermodynamic CALPHAD calculations and results showed that two FCC HEAs compositions (Cr0.18Fe0.27Mn0.275Ni0.275, Cr0.15Mn0.15Fe0.35Ni0.35) and one light refractory metal composition (NbTaTiV) are forming single phase at 600ºC. The FCC alloys has similar mechanical properties to SS316 but with enhanced radiation damage resistance. Refractory metal HEAs show show excellent compressive ductility, and the single phase remained stability after radiation damage. Furthermore, the BCC structure should also lead to lower void swelling rates compared to its FCC counterparts. The samples will be irradiated with Fe2+ ions to understand the alloys’ stability at high radiation damage levels (10, 50, and 100). The irradiation will be performed at 100ºC (close to RT to avoid grain growth) and at 700ºC to simulate the actual operating conditions in SFR reactors. In addition, proton irradiation will be performed to understand the HEAs response to neutron-like damage in normal operating conditions at 700ºC with radiation damage at 0.1 and 0.5 dpa.
Potential impact: HEAs are new class of alloys that has high configurational entropy and atomic-level stresses arising from local lattice mismatches, which allow them to provide additional avenues to annihilate defects and dissipate heat and so resist radiation damage. Such behavior is well know but the proposal is focusing on keys aspects that need to be addressed before using HEAs in SFR systems. The proposal will compare the radiation response of FCC and BCC HEAs to understand the role of the crystal structure in the defect dynamics. The proposal will compare equimolar and non-equimolar alloys to understand the effect of stoichiometry on the defect cascades propagations. And finally, the proposal will compare in general the radiation damage in HEAs compare to conventional binary alloys.
Expected period of performance: The total number of irradiation is estimated to be 24 and we expect to finish that within three months of the award. All the samples have been prepared and are ready for the irradiation experiments.
What is the anticipated scientific outcome from this experiment? The proposal aims to provide a deep understanding of the radiation damage processes in HEAs with different constituent elements, crystal structure, stoichiometry, and at various radiation damage levels.
추가 정보
| 필드 | 값 |
|---|---|
| Abstract | Methods: We have investigated various composition of FCC and BCC HEAs using thermodynamic CALPHAD calculations and results showed that two FCC HEAs compositions (Cr0.18Fe0.27Mn0.275Ni0.275, Cr0.15Mn0.15Fe0.35Ni0.35) and one light refractory metal composition (NbTaTiV) are forming single phase at 600ºC. The FCC alloys has similar mechanical properties to SS316 but with enhanced radiation damage resistance. Refractory metal HEAs show show excellent compressive ductility, and the single phase remained stability after radiation damage. Furthermore, the BCC structure should also lead to lower void swelling rates compared to its FCC counterparts. The samples will be irradiated with Fe2+ ions to understand the alloys’ stability at high radiation damage levels (10, 50, and 100). The irradiation will be performed at 100ºC (close to RT to avoid grain growth) and at 700ºC to simulate the actual operating conditions in SFR reactors. In addition, proton irradiation will be performed to understand the HEAs response to neutron-like damage in normal operating conditions at 700ºC with radiation damage at 0.1 and 0.5 dpa. Potential impact: HEAs are new class of alloys that has high configurational entropy and atomic-level stresses arising from local lattice mismatches, which allow them to provide additional avenues to annihilate defects and dissipate heat and so resist radiation damage. Such behavior is well know but the proposal is focusing on keys aspects that need to be addressed before using HEAs in SFR systems. The proposal will compare the radiation response of FCC and BCC HEAs to understand the role of the crystal structure in the defect dynamics. The proposal will compare equimolar and non-equimolar alloys to understand the effect of stoichiometry on the defect cascades propagations. And finally, the proposal will compare in general the radiation damage in HEAs compare to conventional binary alloys. Expected period of performance: The total number of irradiation is estimated to be 24 and we expect to finish that within three months of the award. All the samples have been prepared and are ready for the irradiation experiments. What is the anticipated scientific outcome from this experiment? The proposal aims to provide a deep understanding of the radiation damage processes in HEAs with different constituent elements, crystal structure, stoichiometry, and at various radiation damage levels. |
| Award Announced Date | 2018-05-17T10:58:15.237 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kumar Sridharan |
| Irradiation Facility | None |
| PI | Mohamed Elbakhshwan |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 1394 |