NSUF 16-638: Influence of neutron irradiation on the microstructures and electrical properties of polymer derived ceramic sensing material
The objective of this project is to perform neutron irradiation damage test on one kind of polymer derived SiAlCN ceramics (PDC). If our hypothesis is correct -- the microstructures and electrical properties are maintained under irradiation -- such material will later be designed as a temperature sensor in nuclear reactor for in-core temperature measurement (It will be the goal for the next phase). In this phase of project, irradiation experiments will be performed at PULSTAR reactor at North Carolina State University (NCSU). Temperature sensors for nuclear reactor applications are subject to high temperature, high pressure, and irradiation challenges. Currently, wired thermocouples are the most common temperature sensor used in nuclear reactors. The current nuclear field has made significant advances in thermocouple design, but there are still limitations in durability and increased expense in instrumented test assemblies. In our previous work, we have been able to demonstrate that SiAlCN materials pertains good semiconducting behaviors and good thermal resistance up to 1050 oC. Both leaded and wireless sensors have been designed and experimented with excellent accuracy for a duration of time (10 hours). Even more appealing, the crystallinity and composition of SiAlCN materials can be adjusted and controlled to modify the electrical conducting properties and sensitivity gauging factor. This proposed work intends to test the irradiation stability of such ceramic sensing materials, and if successful, in the next step, we will design a temperature sensor based on such material for nuclear reactor temperature measurement. Irradiation stability is one of the most important factors to ensure the performance of the PDC sensor material for nuclear application. PDCs are mostly used at non-crystalline state, which makes them less brittle. PDCs also exhibit a more stable structure than crystalline SiC and Si3N4, which is inferred from their higher creep resistance and higher thermal stability. Unlike conventional materials, the PDCs consist of nano-domains created by intertwined graphene (aromatic carbon) sheets about 1-5nm in size. The unique structure of PDCs can effectively promote defect recombination to mitigate radiation damage. During this task, we will assess the irradiation tolerance, microstructural stability and electric properties of PDC material to understand the radiation effects on its sensing capability. In total, it will take six months to perform this research, including (1) sample preparation, (2) material property characterization before irradiation test, (3) perform Irradiation test, (4) material property characterization after irradiation test, data analysis, and material properties comparison, and (5) finishing documentation and research summary. Scanning Electron Microscope (SEM) and Optical Microscopes (OM) will be used to examine the surface of irradiated samples. X-Ray Diffraction (XRD) will be used to investigate the possible irradiation induced crystallinity change in the sample, in which case, further Transmission Electron Microscopy (TEM) investigations will be used. Based on the radiation test results and PIE analysis, further optimization on material composition and fabrication process will be performed to ensure its irradiation stability in such harsh nuclear environment.
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of this project is to perform neutron irradiation damage test on one kind of polymer derived SiAlCN ceramics (PDC). If our hypothesis is correct -- the microstructures and electrical properties are maintained under irradiation -- such material will later be designed as a temperature sensor in nuclear reactor for in-core temperature measurement (It will be the goal for the next phase). In this phase of project, irradiation experiments will be performed at PULSTAR reactor at North Carolina State University (NCSU). Temperature sensors for nuclear reactor applications are subject to high temperature, high pressure, and irradiation challenges. Currently, wired thermocouples are the most common temperature sensor used in nuclear reactors. The current nuclear field has made significant advances in thermocouple design, but there are still limitations in durability and increased expense in instrumented test assemblies. In our previous work, we have been able to demonstrate that SiAlCN materials pertains good semiconducting behaviors and good thermal resistance up to 1050 oC. Both leaded and wireless sensors have been designed and experimented with excellent accuracy for a duration of time (10 hours). Even more appealing, the crystallinity and composition of SiAlCN materials can be adjusted and controlled to modify the electrical conducting properties and sensitivity gauging factor. This proposed work intends to test the irradiation stability of such ceramic sensing materials, and if successful, in the next step, we will design a temperature sensor based on such material for nuclear reactor temperature measurement. Irradiation stability is one of the most important factors to ensure the performance of the PDC sensor material for nuclear application. PDCs are mostly used at non-crystalline state, which makes them less brittle. PDCs also exhibit a more stable structure than crystalline SiC and Si3N4, which is inferred from their higher creep resistance and higher thermal stability. Unlike conventional materials, the PDCs consist of nano-domains created by intertwined graphene (aromatic carbon) sheets about 1-5nm in size. The unique structure of PDCs can effectively promote defect recombination to mitigate radiation damage. During this task, we will assess the irradiation tolerance, microstructural stability and electric properties of PDC material to understand the radiation effects on its sensing capability. In total, it will take six months to perform this research, including (1) sample preparation, (2) material property characterization before irradiation test, (3) perform Irradiation test, (4) material property characterization after irradiation test, data analysis, and material properties comparison, and (5) finishing documentation and research summary. Scanning Electron Microscope (SEM) and Optical Microscopes (OM) will be used to examine the surface of irradiated samples. X-Ray Diffraction (XRD) will be used to investigate the possible irradiation induced crystallinity change in the sample, in which case, further Transmission Electron Microscopy (TEM) investigations will be used. Based on the radiation test results and PIE analysis, further optimization on material composition and fabrication process will be performed to ensure its irradiation stability in such harsh nuclear environment. |
| Award Announced Date | 2016-04-11T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Ayman Hawari |
| Irradiation Facility | None |
| PI | Cheryl Xu |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 638 |