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TECHNICAL PAPERS

Prediction of Materials Damage History From Stress Corrosion Cracking in Boiling Water Reactors

[+] Author and Article Information
Iouri Balachov, Digby Macdonald

Center for Advanced Materials, Pennsylvania State University, 517B Deike Building, University Park, PA 16802

Bernhard Stellwag, Norbert Henzel, Renate Kilian

Power Generation Group (KWU), Siemens AG, D-91050 Erlangen, Germany

J. Pressure Vessel Technol 122(1), 45-49 (Oct 11, 1999) (5 pages) doi:10.1115/1.556148 History: Received September 16, 1998; Revised October 11, 1999
Copyright © 2000 by ASME
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Figures

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Structure of the algorithm
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Predicted histories of growing cracks in the lower plenum of an operating boiling water reactor. Location no. 1 is at the bottom of the internal pump, and location no. 9 is at the bottom (entrance) to the core. Intermediate locations (nos. 3, 5, and 7) represent regions near the bottom of the reactor vessel and at various elevations along control rod drive structures.
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Predicted effect of HWC (feedwater [H2]=0.5 ppm) on the accumulated damage. The initial value of the crack length (0.5 cm, 0.197 in.) may be considered to be the depth of a detected crack, and the time in years as the remaining (extended) service time after introducing HWC.

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