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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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.

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