NSUF 17-1052: Study of the factors affecting the radiation tolerance of MAX phases for innovative fuel cladding concepts
This project aims at understanding the factors affecting the radiation tolerance of MAX phases for fuel cladding applications. To this end, ‘model alloys’ with the same stoichiometry but distinctly different microstructures will be simultaneously ion-irradiated, so as to demonstrate the impact of grain size distribution and texture on the radiation tolerance of MAX phases. Ion irradiation will be carried out at two different temperatures, i.e., 350C and 600C; the former is relevant to the nominal service conditions of fuel clads for Gen-II/III light water reactors (LWRs); the latter is relevant to the (anticipated) nominal service conditions of fuel clads for Gen-IV lead fast reactors (LFRs). The use of MAX phases in innovative fuel cladding concepts is considered in order to address important material challenges in the nuclear sector, such as the development of accident-tolerant fuel (ATFs) clads for Gen-II/III LWRs and liquid metal corrosion-resistant fuel clads for Gen-IV LFRs. The phase-pure ‘model alloys’ to be ion irradiated at the Michigan Ion Beam Laboratory (MIBL) are the ternary carbide Nb4AlC3 and its solid solution (Nb0.85,Zr0.15)4AlC3. It follows that the proposed experiments will also help to shed light on the effects of MAX phase alloying on the radiation tolerance. The targeted displacement dose is about 40 dpa, so as to produce data that are relevant for fuel cladding applications. This ion irradiation campaign is also designed to assess the materials’ resistance to decomposition, amorphisation and swelling. The proposed ion irradiation will be completed within 6 months after the project selection; the irradiated matter will be subjected to post-irradiation examination (PIE) by means of TEM/STEM. The suggested ion irradiation and ensuing PIE are expected to demonstrate the suitability of MAX phases for nuclear fuel cladding applications, thus opening the road to their further development and qualification. The findings of the herein proposed work are expected to provide a fundamental understanding of the factors (microstructure, alloying) affecting the radiation tolerance of the MAX phases. The importance of this study is not limited to specific compounds in the Nb-Zr-Al-C system, since it is reasonable to expect that the conclusions of this study are transferable to other members of the MAX phase family and will be exploited during the development and optimisation of MAX phases with coolant-specific stoichiometries, so as to effectively address material property requirements such as oxidation and corrosion resistance.
Additional Info
| Field | Value |
|---|---|
| Abstract | This project aims at understanding the factors affecting the radiation tolerance of MAX phases for fuel cladding applications. To this end, ‘model alloys’ with the same stoichiometry but distinctly different microstructures will be simultaneously ion-irradiated, so as to demonstrate the impact of grain size distribution and texture on the radiation tolerance of MAX phases. Ion irradiation will be carried out at two different temperatures, i.e., 350C and 600C; the former is relevant to the nominal service conditions of fuel clads for Gen-II/III light water reactors (LWRs); the latter is relevant to the (anticipated) nominal service conditions of fuel clads for Gen-IV lead fast reactors (LFRs). The use of MAX phases in innovative fuel cladding concepts is considered in order to address important material challenges in the nuclear sector, such as the development of accident-tolerant fuel (ATFs) clads for Gen-II/III LWRs and liquid metal corrosion-resistant fuel clads for Gen-IV LFRs. The phase-pure ‘model alloys’ to be ion irradiated at the Michigan Ion Beam Laboratory (MIBL) are the ternary carbide Nb4AlC3 and its solid solution (Nb0.85,Zr0.15)4AlC3. It follows that the proposed experiments will also help to shed light on the effects of MAX phase alloying on the radiation tolerance. The targeted displacement dose is about 40 dpa, so as to produce data that are relevant for fuel cladding applications. This ion irradiation campaign is also designed to assess the materials’ resistance to decomposition, amorphisation and swelling. The proposed ion irradiation will be completed within 6 months after the project selection; the irradiated matter will be subjected to post-irradiation examination (PIE) by means of TEM/STEM. The suggested ion irradiation and ensuing PIE are expected to demonstrate the suitability of MAX phases for nuclear fuel cladding applications, thus opening the road to their further development and qualification. The findings of the herein proposed work are expected to provide a fundamental understanding of the factors (microstructure, alloying) affecting the radiation tolerance of the MAX phases. The importance of this study is not limited to specific compounds in the Nb-Zr-Al-C system, since it is reasonable to expect that the conclusions of this study are transferable to other members of the MAX phase family and will be exploited during the development and optimisation of MAX phases with coolant-specific stoichiometries, so as to effectively address material property requirements such as oxidation and corrosion resistance. |
| Award Announced Date | 2017-09-20T12:34:26.727 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kevin Field |
| Irradiation Facility | None |
| PI | Konstantina Lambrinou |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 1052 |