Abstract
This chapter focuses on the modeling of pellet–cladding interaction (PCI) in pressurized water reactor under nominal and transient loading conditions. Scientific results proposed in this chapter have already been published and are mainly based on an important experimental and research cooperative program between EDF, AREVA, and the Atomic Energy Commission CEA which was initiated to get a better understanding of the mechanisms possibly leading to PCI failure, as well as to qualify a PCI-resistant rod design.
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