Texto completo de evento
PCMI effect study in the fuel rod of a PWR reactor type subjected to power ramps
Autor
BERRETTA, JOSE R.
LIMA, LEONARDO S.
REIS, REGIS
AGUIAR, AMANDA A.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Resumen
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.