“…Te and Sb were first absorbed in zircaloy cladding, then they were released through cladding oxidation [24]. In another representative test series, the HEVA/VERCORS tests, the fuel specimens were re-irradiated in research reactors in order to investigate the release behaviour of short-lived FPs such as 131 I, 133 I, 132 Te, 99 Mo, 140 Ba and 140 La that were not accurately investigated in the ORNL HI/VI tests [25][26][27]. The HEVA/VERCORS tests gave the following results.…”