Stability of Circumferential Flaws in Once-Through Steam Generator Tubes Under Thermal Loading During LOCA, MSLB and FWLB (NUREG/CR-7225)
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Publication Information
Manuscript Completed: December 2010
Date Published: November 2017
Prepared by:
Saurin Majumdar
Argonne National Laboratory
Argonne, IL 60439
Matt Rossi, NRC Project Manager
NRC Job Code Y6582
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington DC 20555-0001
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Abstract
Axial thermal loads during loss of coolant, main steam line break and feed water line break accident conditions may cause circumferential flaws in steam generator tubes to sever in once-through steam generators (OTSGs). Finite element models were used to examine the combined effects of thermal loads, tube size, flaw size, and accident conditions that result in tube failure.
Page Last Reviewed/Updated Tuesday, March 09, 2021