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University of Birmingham > Talks@bham > Nuclear physics seminars > Monitoring Radiation Damage in Material For Accident-Tolerant Nuclear Fuels
![]() Monitoring Radiation Damage in Material For Accident-Tolerant Nuclear FuelsAdd to your list(s) Download to your calendar using vCal
If you have a question about this talk, please contact Tzany Kokalova Wheldon. The explosions at Fukushima where the direct result of interactions between water and the Zr cladding on the fuel that led to the production of hydrogen gas at high temperature. A large research effort to develop accident tolerant fuels for use in light water reactors has been undertaken to attempt to develop fuels that are safer under accident conditions. Our research group has looked at potential claddings such as ZrC, ZrN, and SiC. Specifically, we are trying to develop experimental methods that provide data that can be used by modelers to evaluate the performance of reactor components in extreme environments (temperature, neutron flux, chemistry). In our lab, we are growing materials, then studying their behavior under these extreme conditions. We work with theorists to adjust models to better predict the experimental results. This talk will focus on ZrC and SiC that may be used in TRISO fuel applications. This talk is part of the Nuclear physics seminars series. This talk is included in these lists:Note that ex-directory lists are not shown. |
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