United States Nuclear Regulatory Commission - Protecting People and the Environment

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 Wednesday, November 22, 2017