NSUF 09-204: Advanced Damage Tolerant Ceramics: Candidates for Nuclear Structural Applications
The demands of Gen IV nuclear power plants for long service life under neutron radiation at hightemperature are severe. Advanced materials that would withstand high temperatures (up to 1000°C) to high doses in a neutron field would be ideal for reactor internal structures and would add to the long service life and reliability of the reactors. In this proposal, the response of a new class of machinable, conductive, layered, ternary transition metal carbides and nitrides – the so-called MAX phases - to neutron will be explored at temperatures up to 1000°C as a function of neutron fluence. The microstructures, electrical resistivity, and tensile strength of select MAX phases will be characterized following irradiation up to 7.0 x 10^21 n/cm2 (En > 0.1 MeV) at ~100, 500, and 1000°C in a research reactor. The proposed work would compliment research scheduled for lower temperatures and fluence at the MITR on neutron damage of this potentially important class of high temperature solids. Samples will be prepared at the leading university and neutron irradiated in a university reactor. The post-irradiation microstructures, resistivity and tensile properties will be characterized at the post-irradiation facilities at INL and SRNL. This work will provide a solid base of information to characterize the irradiation response of the MAX phases and provide a comparison to leading ceramics proposed for Gen IV in-core components in a high temperature environment. The MAX phases may prove to be superior materials for select in-reactor component design, especially with their creep resistance well beyond 1000ºC.
Mer information
| Fält | Värde |
|---|---|
| Awarded Institution | Drexel University |
| Embargo End Date | 2026-02-27 |
| Facility Tech Lead | Alina Montrose, Mukesh Bachhav |
| NSUF Call | FY 2009 Spring Solicitation for User Proposals |
| PI | Michel Barsoum |
| Project Member | Elizabeth Hoffman - Savannah River National Laboratory |
| Project Member | Michel Barsoum - Drexel University (https://orcid.org/0000-0001-7800-3517) |
| Project Type | Irradiation/PIE |
| Publication | Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121-1085 C temperature range Michel Barsoum, Jian Gan, Elizabeth Hoffman, Darin Tallman, Lingfeng He Journal of Nuclear Materials 484 2017-02-01 http://www.sciencedirect.com/science/article/pii/S0022311516311370 |
| Publication | Effect of neutron irradiation on defect evolution in Ti3SiC2 and Ti2AlC Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman Journal of Nuclear materials 468 2015-10-23 https://www.sciencedirect.com/science/article/pii/S0022311515302786 |
| Publication | Microstructural Defects in Neutron Irradiated Ti3SiC2 and Ti2AlC Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman ICACC'15 2015-01-25 - 2015-01-29 |
| Publication | Effect of neutron irradiation on select MAX phases Michel Barsoum, Elizabeth Hoffman, Gordon Kohse, Darin Tallman Acta Materialia 85 2014-10-29 https://www.sciencedirect.com/science/article/pii/S1359645414008477 |
| RTE Number | 204 |