Published January 1997 | Version v1
Report Restricted

On the issue of Zircaloy ductility during a reactivity-initiated accident

  • 1. Pennsylvania State Univ., University Park, PA (United States)

Description

During reactor exposure, Zircaloy cladding undergoes various microstructural changes including irradiation damage, oxidation, and hydrogen pick-up. There is a concern that the combination of these changes in high burnup cladding will cause failure during a reactivity-initiated accident (RIA) at an energy deposition level significantly lower than that of fresh cladding. In RIA conditions, the cladding must withstand loading at high strain rates and under deformation paths close to transverse plane-strain extension. Thus to assess cladding failure it is necessary to examine the failure mechanism of unirradiated Zircaloy cladding under RIA-like loading conditions. The authors present here a theoretical analysis of a possible failure mode of Zircaloy cladding due to localized necking. The results of the analysis suggest that high-burnup cladding is susceptible to pronounced losses of ductility under a combination of plane strain loading deformation and the presence of thickness imperfections. Such imperfections may be caused by hydride embrittlement of the cladding or non-uniform oxidation such that an axial thickness change is created

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Additional details

Publishing Information

Imprint Title
Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging
Imprint Pagination
372 p.
Journal Page Range
p. 141-149.
Report number
NUREG/CP--0157-Vol.1

Conference

Title
24. water reactor safety information meeting.
Dates
21-23 Oct 1996.
Place
Bethesda, MD (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28066956
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DUCTILITY; FAILURE MODE ANALYSIS; FUEL CANS; ZIRCALOY
Descriptors DEC
ALLOYS; MECHANICAL PROPERTIES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TENSILE PROPERTIES; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Contract/Grant/Project number
Grant NRC-04-95-068
Secondary number(s)
CONF-9610202--Vol.1.