Abstract
Three post-irradiation heating tests of fuel compacts from the US AGR-3/4 irradiation experiment. In addition to TRISO-coated driver fuel, each compact contained 20 particles with UCO fuel kernels coated only in pyrocarbon to simulate exposed kernels. Tests at 1600/1700°C, 1400°C, and 1200°C were performed to measure fission product releases as a function of time and temperature. Silver releases were highest in the 1200°C test, supporting the observation that silver release rates are highest in the temperature range of 1100-1300°C. Except for Ag-110m (which was released in multiple particle equivalents) releases of Cs, Kr, Eu, and Sr were all less than one particle inventory per compact. This suggests that exposed kernels retain little Cs and Kr after irradiation. Despite these low releases, compared to tests of compacts with no exposed kernels, the Cs and Kr releases were noticeably higher, and at 1600°C the exposed kernels contributed noticeably more Eu and Sr than in AGR-1 compacts with no exposed kernels. These data can be used to make inferences on retention of fission products in exposed kernels.
| Original language | English |
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| State | Published - Oct 1 2018 |
| Event | HTR 2018 - International Conference on High Temperature Reactor Technology - Warsaw, Poland Duration: Oct 8 2018 → Oct 11 2018 |
Conference
| Conference | HTR 2018 - International Conference on High Temperature Reactor Technology |
|---|---|
| Country/Territory | Poland |
| City | Warsaw |
| Period | 10/8/18 → 10/11/18 |
INL Publication Number
- INL/CON-18-44692