{'fraction_non_alphanumeric': 0.01581325301204819, 'fraction_numerical': 0.0338855421686747, 'mean_word_length': 5.040909090909091, 'pattern_counts': {'":': 0, '<': 0, '<?xml version=': 0, '>': 0, 'https://': 0, 'lorem ipsum': 0, 'www.': 0, 'xml': 0}, 'pii_count': 0, 'substrings_counts': 0, 'word_list_counts': {'cursed_substrings.json': 0, 'profanity_word_list.json': 0, 'sexual_word_list.json': 0, 'zh_pornsignals.json': 0}}
Structure-Phase Changes and Corrosion Behavior of E110 and E635 Claddings of Fuels in Water Cooled Reactors

Data are discussed pertaining to influence of in-pile irradiation on microstructure, tensile and corrosion properties of E110 and E635 cladding samples taken along fuel rods that have operated for ~5 and 3 years in RBMK and VVER-1000 reactors, respectively. In the initial condition the E110 cladding structure was a recrystallized one while that of E635 was partially re-crystallized. Irradiation has lead to the almost full recrystallization of the E635 alloy cladding. The original structure basically comprising a-type dislocation transforms into the structure that features the high density of the a-type dislocation loops. No dislocations of the c-type were identified in the cladding samples of both the alloys. Changes in the composition of the β-Nb particles in the E110 alloy claddings and changes in Laves phase particle composition in the E635 claddings were revealed. The results on the in-pile corrosion of the E110 and E635 claddings are reviewed in comparison to the results of the autoclave tests. The interrelation is discussed between the irradiation hardening and irradiation induced corrosion of E110 and E635 claddings as attended by the evolution of the structure-phase condition of those alloys.