The influence of hydrogen on oxygen distribution inside Zry-4 fuel cladding

Negyesi, Martin; Burda, Jaroslav V.; Bláhová, Olga; Linhart, S.; Vrtílková, Věra

doi:10.1016/j.jnucmat.2011.06.013

Cited by 11 publications

(1 citation statement)

References 9 publications

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“…Zirconium alloys have been extensively used in fuelcladding and structural materials in nuclear power reactors [1][2][3][4][5][6][7] as they have a low absorption cross section for the thermal neutrons. To improve the performance of zircaloy in extremely hazardous environments, different zircaloys with different alloyed elements have been developed in recent decades, including ZIRLO, [8] E635, [9] M5, [2,10] Zr-4, [2,[4][5][6] and Zr-2.…”

Section: Introductionmentioning

confidence: 99%

Microstructure evolution of zircaloy-4 during Ne ion irradiation and annealing: Anin situTEM investigation

Shen¹,

Peng²,

Zhou³

et al. 2014

Chinese Phys. B

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The microstructural evolution of zircaloy-4 was studied, including the amorphization and recrystallization of Zr(Fe, Cr) 2 precipitates, and the density of dislocations under in situ Ne ion irradiation and post annealing. The results show that irradiation at a relatively high temperature and dose induces the formation of nanocrystals in pre-amorphized Zr(Fe, Cr) 2 precipitates. The recrystallized nanocrystals also have the structure of hcp-Zr(Fe, Cr) 2 . The formation of the nanocrystals is thought to be the consequence of competition between atomistic disordering and the recrystallization of precipitates under ion irradiation. The free energy of the nanocrystal is lower than that of the amorphous state, which is another reason for the recrystallization of the precipitates. With increased annealing temperature, the density of the nanocrystals is increased. The dislocation density sharply decreases with the increase in the annealing temperature, and its size increases.

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