Performance of AGR-1 high-temperature reactor fuel during post-irradiation heating tests
Nuclear Engineering and Design（2016）
摘要
•High-temperature safety tests were performed on 14 irradiated HTGR fuel compacts.•Significant krypton release was detected in only one of the safety tests.•Cesium retention by intact SiC was excellent, even up to 1800°C.•Release of Ag, Eu, and Sr was dominated by previous release during irradiation.•Silver exhibited the highest fractional release.
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