Abstract
In its regulations for commercial power reactors, the U.S. Nuclear Regulatory Commission (NRC) specifies criteria to ensure that fuel cladding maintains a degree of post-quench ductility (PQD) during a postulated loss-ofcoolant accident (LOCA). The current criteria, 2200oF (1204oC) and 17-percent equivalent cladding reacted (ECR), are based on tests performed on 1970s-vintage unirradiated Zircaloy specimens. In 1996, the NRC initiated an extensive LOCA research program to investigate potential burnup and alloy effects on the current criteria. The results of this research are summarized in several publicly available documents.Based on these results, the NRC has developed specific rule-change objectives, which are summarized here, to address deficiencies in the current criteria and has outlined a schedule for implementing the necessary changes.
Published Version
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