NSUF 09-152: Radiation Stability of Ceramics for Advanced Fuel Applications
Fuel irradiation performance is one of the key issues for supporting the goals of the Advanced Fuel Cycle Initiative (AFCI) and the Deep-Burn (DB) concept for the Very High Temperature reactor. ZrC, TiC, ZrN and TiN were selected as the candidates with the highest potential for success as carbide and nitridebased composite-type fuels and pin-type refractory ceramic fuel for the gas-cooled fast reactor (GFR). In addition, ZrC is also an alternative, higher temperature material for the fuel kernel and/or coating system in microencapsulated coated particle fuels for Very High Temperature Reactor (VHTR). All four could be considered as inert matrix materials for advanced non-fertile fuel. Determining and predicting the stability in response to radiation is a key part in developing a practical ceramics-based fuel, nevertheless, very few studies of radiation tolerance on these ceramics is available and the detailed microstructural analysis following neutron irradiation is not published. This research proposes to investigate the microstructural evolution of the ZrC, TiC, ZrN, and TiN irradiated in the ATR at the temperature of 800ºC to dose of 1dpa. These materials are currently available in the ATR PIE library. Both 3mm discs and 20mm rods are available and can be used for the microstructural study, micro-hardness testing and immersion density measurements. The microstructural analysis will be performed using analytical transmission electron microscopy (TEM) to determine changes in lattice constant, changes in dislocation density and size, identify new precipitates, phase changes, or amorphization, and identify any void nucleation and growth. The microhardness testing will be performed using the micro-indenter, and immersion density measurement will also be performed for estimation of volumetric swelling. These experimental efforts are proposed to be a one year project. This investigation of the ATR neutron irradiated ceramics will provide some of the first neutron irradiation effects data ever for multiple candidate fuel matrix and coating materials. The microstructural analysis from the ATR samples can be compared to those created using proton irradiation as part of an ongoing NERI project. This research would not only provide a basis for which to better understand the microstructural evolution under an intended neutron environment, but would also provide insight into the validity of using ion irradiation to understand the radiation effects of energetic neutrons in refractory ceramics.
Additional Info
| Field | Value |
|---|---|
| Abstract | Fuel irradiation performance is one of the key issues for supporting the goals of the Advanced Fuel Cycle Initiative (AFCI) and the Deep-Burn (DB) concept for the Very High Temperature reactor. ZrC, TiC, ZrN and TiN were selected as the candidates with the highest potential for success as carbide and nitridebased composite-type fuels and pin-type refractory ceramic fuel for the gas-cooled fast reactor (GFR). In addition, ZrC is also an alternative, higher temperature material for the fuel kernel and/or coating system in microencapsulated coated particle fuels for Very High Temperature Reactor (VHTR). All four could be considered as inert matrix materials for advanced non-fertile fuel. Determining and predicting the stability in response to radiation is a key part in developing a practical ceramics-based fuel, nevertheless, very few studies of radiation tolerance on these ceramics is available and the detailed microstructural analysis following neutron irradiation is not published. This research proposes to investigate the microstructural evolution of the ZrC, TiC, ZrN, and TiN irradiated in the ATR at the temperature of 800ºC to dose of 1dpa. These materials are currently available in the ATR PIE library. Both 3mm discs and 20mm rods are available and can be used for the microstructural study, micro-hardness testing and immersion density measurements. The microstructural analysis will be performed using analytical transmission electron microscopy (TEM) to determine changes in lattice constant, changes in dislocation density and size, identify new precipitates, phase changes, or amorphization, and identify any void nucleation and growth. The microhardness testing will be performed using the micro-indenter, and immersion density measurement will also be performed for estimation of volumetric swelling. These experimental efforts are proposed to be a one year project. This investigation of the ATR neutron irradiated ceramics will provide some of the first neutron irradiation effects data ever for multiple candidate fuel matrix and coating materials. The microstructural analysis from the ATR samples can be compared to those created using proton irradiation as part of an ongoing NERI project. This research would not only provide a basis for which to better understand the microstructural evolution under an intended neutron environment, but would also provide insight into the validity of using ion irradiation to understand the radiation effects of energetic neutrons in refractory ceramics. |
| Award Announced Date | 2009-02-04T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Alina Zackrone, Kumar Sridharan |
| Irradiation Facility | None |
| PI | Yong Yang |
| PI Email | [email protected] |
| Project Type | PIE Only |
| RTE Number | 152 |