PCMI effect study in the fuel rod of a PWR reactor type subjected to power ramps
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2019
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
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Resumo
PWR reactor type, when subjected to the power ramp regime, a mechanical interaction between the cladding
and the UO2 pellet (PCMI) may occur in the fuel rod. To investigate this phenomenon were used two softwares,
the first was a modified fuel performance code to verify the behavior of fuel rod with steel cladding and another
to analyze structural mechanical behavior. The fuel performance code results show that there is no contact
between the pellet and the cladding in the fuel rod, considering the estimated burning under normal conditions
of reactor operation. Thus, it was adopted the hypothesis of the interaction pellet-cladding occurrence,
generated by pellet fragmentation and relocation, and power ramp simulation conditions independent of the
ramp time. The simulations results show that the fuel rod maintains its integrity under the conditions of the
adopted hypothesis.
Como referenciar
BERRETTA, JOSE R.; LIMA, LEONARDO S.; REIS, REGIS; AGUIAR, AMANDA A. PCMI effect study in the fuel rod of a PWR reactor type subjected to power ramps. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5270-5275. Disponível em: http://repositorio.ipen.br/handle/123456789/30714. Acesso em: 20 Mar 2026.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.