Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys
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2019
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
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In pressurized water reactors (PWR) the fuel rod cladding is the first barrier against the spread of
fission
products. It is therefore essential to guarantee its use in the reactor. Sometimes the production of electricity
requires that certain power plants operate in “network monitoring”. The fuel introduced into nuclear power
reactors can then undergo so metimes significant power variations. Following a severe reactor power transient,
clad failure can occur through a stress corrosion phenomenon (SCC), under the combined action of mechanical
stresses and gaseous fission products generated by the fuel pellets. Among those iodine plays a major role, for it
may induce SCC in zircaloy. In the early ages of water cooled reactors (PWRs, BWRs or CANDU), series of
similar failures took place following sharp startups. Today power increase rates as well as instantaneous local
power levels are limited. Indeed, it is well know that cladding failure by iodine induced stress corrosion
cracking (I SCC) may occur under pellet cladding interactions (PCI) conditions during power transients in
PWRs. In this paper we review the advances in the understanding of these SCC cracking mechanisms of the
fuel rod cladding that would then allow better control of the integrity of the clad during the more severe
demands related to the operating conditions of th e PWRs.
Como referenciar
LOBO, RAQUEL de M.; ANDRADE, ARNALDO H.P. de. Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5339-5345. Disponível em: http://repositorio.ipen.br/handle/123456789/30719. Acesso em: 23 Mar 2025.
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