Fracture analysis of the heat-affected zone in the NESC-1 spinning cylinder experiment

Journal Article · Mon Feb 01 04:00:00 EST 1999 · Journal of Pressure Vessel Technology

DOI:https://doi.org/10.1115/1.2883662· OSTI ID:328395

Keeney, J A ^[1]

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1. Oak Ridge National Lab., TN (United States)

This paper presents updated analyses of the cylinder specimen being used in the international Network for Evaluating Steel Components (NESC) large-scale spinning-cylinder project (NESC-1). The NESC was organized as an international forum to exchange information on procedures for structural integrity assessment, to collaborate on specific projects, and to promote the harmonization of international standards. The objective of the NESC-1 project is to focus on a complete procedure for assessing the structural integrity of aged reactor pressure vessels. A clad cylinder containing through-clad and subclad cracks will be tested under pressurized-thermal shock conditions at AEA Technology, Risley, U.K. Three-dimensional finite-element analyses were carried out to determine the effects of including the cladding heat-affected zone (HAZ) in the models. The cylinder was modeled with inner-surface through-clad cracks having a depth of 74 mm and aspect ratios of 2:1 and 6:1. The cylinder specimen was subjected to centrifugal loading followed by a thermal shock and analyzed with a thermoelastic-plastic material model. The peak K{sub 1} values occurred at the clad/HAZ interface for the 6:1 crack and at the HAZ/base interface for the 2:1 crack. The analytical results indicate that cleavage initiation is likely to be achieved for the 6:1 crack, but questionable for the 2:1 crack.

• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 328395
• Journal Information: Journal of Pressure Vessel Technology, Journal Name: Journal of Pressure Vessel Technology Journal Issue: 1 Vol. 121; ISSN 0094-9930; ISSN JPVTAS
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
AGING
CLEAVAGE
CRACKS
FINITE ELEMENT METHOD
FRACTURE MECHANICS
HEAT AFFECTED ZONE
LOSS OF COOLANT
PRESSURE VESSELS
PROTECTIVE COATINGS
RELIABILITY
STEELS
THERMAL SHOCK