NSUF 21-4280: Microstructural Examination of Irradiation Effects on Metal Matrix Composite Neutron Absorber
This project proposes to conduct post-irradiation examination of HfAl3 Al composite specimens previously irradiated at the Advanced Test Reactor. Particles comprised of a thermal neutron absorbing material (HfAl3) are dispersed in a metal matrix material with high thermal conductivity (aluminum) to conduct the heat generated by neutron capture away from the fuel and materials. This MMC is very promising for use as a conduction-cooled neutron absorber and has the potential to be useful as a shroud or heat sink for testing advanced fast reactor fuels and materials in an existing thermal reactor. Through post-irradiation examination (PIE), mechanical and thermophysical properties have been characterized and many features of the microstructure have been determined and compared with those of the unirradiated material. However, to publish the previously obtained tensile data, we need a few more pieces of data as described below to address reviewer comments. Publication of this data is important to archive the investment that NSUF has already put into irradiating this material as part of two irradiation campaigns. Results from this research will be used to provide fundamental understanding of the irradiation effect on material properties. Such information is necessary before proceeding with design and optimization of an absorber block system for advanced reactor designs, such as those currently being proposed by a number of vendors. The focus of this proposal is to obtain very focused, essential data to help us understand the structure, chemistry and properties of this metal matrix composite material. The NSUF has invested significant resources towards the characterization of the thermal properties of this material. However, the PIE is incomplete until we resolve these remaining technical questions concerning the tensile and hardness data. The overall objective is to determine the effects of radiation damage on the material microstructure, and in turn how the resultant microstructure affects the thermal and mechanical properties of the material, which ultimately affect performance and function of reactor components fabricated from this material. For the intended use of this material, there is a need to understand possible sources of reduced thermal conductivity, the microstructural origin of the irradiation hardening, and document the effect of irradiation on the stability of the HfAl3 dispersion.
Additional Info
| Field | Value |
|---|---|
| Abstract | This project proposes to conduct post-irradiation examination of HfAl3 Al composite specimens previously irradiated at the Advanced Test Reactor. Particles comprised of a thermal neutron absorbing material (HfAl3) are dispersed in a metal matrix material with high thermal conductivity (aluminum) to conduct the heat generated by neutron capture away from the fuel and materials. This MMC is very promising for use as a conduction-cooled neutron absorber and has the potential to be useful as a shroud or heat sink for testing advanced fast reactor fuels and materials in an existing thermal reactor. Through post-irradiation examination (PIE), mechanical and thermophysical properties have been characterized and many features of the microstructure have been determined and compared with those of the unirradiated material. However, to publish the previously obtained tensile data, we need a few more pieces of data as described below to address reviewer comments. Publication of this data is important to archive the investment that NSUF has already put into irradiating this material as part of two irradiation campaigns. Results from this research will be used to provide fundamental understanding of the irradiation effect on material properties. Such information is necessary before proceeding with design and optimization of an absorber block system for advanced reactor designs, such as those currently being proposed by a number of vendors. The focus of this proposal is to obtain very focused, essential data to help us understand the structure, chemistry and properties of this metal matrix composite material. The NSUF has invested significant resources towards the characterization of the thermal properties of this material. However, the PIE is incomplete until we resolve these remaining technical questions concerning the tensile and hardness data. The overall objective is to determine the effects of radiation damage on the material microstructure, and in turn how the resultant microstructure affects the thermal and mechanical properties of the material, which ultimately affect performance and function of reactor components fabricated from this material. For the intended use of this material, there is a need to understand possible sources of reduced thermal conductivity, the microstructural origin of the irradiation hardening, and document the effect of irradiation on the stability of the HfAl3 dispersion. |
| Award Announced Date | 2021-06-07T16:20:42.507 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Yaqiao Wu |
| Irradiation Facility | None |
| PI | Donna Guillen |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 4280 |