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Assessment of U.S. Embrittlement Trend Equations Considering the Latest Available Surveillance Data

[+] Author Affiliations
William L. Server

ATI Consulting, Pinehurst, NC

Randy G. Lott

Westinghouse Electric Company, LLC, Pittsburgh, PA

Stan T. Rosinski

EPRI, Charlotte, NC

Paper No. PVP2004-3053, pp. 19-24; 6 pages
doi:10.1115/PVP2004-3053
From:
  • ASME/JSME 2004 Pressure Vessels and Piping Conference
  • Storage Tank Integrity and Materials Evaluation
  • San Diego, California, USA, July 25–29, 2004
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4685-7
  • Copyright © 2004 by ASME

abstract

The mechanistically-guided embrittlement correlation model adopted in ASTM E 900-02 was based on a database of U.S. surveillance results current through calendar year 1998. There exists now an extensive amount of new surveillance data that includes a large amount of boiling water reactor (BWR) results from an integrated, supplemental surveillance program designed to augment the plant-specific BWR surveillance programs. These recent data allow a statistical test of the ASTM E 900-02 embrittlement correlation, as well as the NRC correlation model currently being used in the pressurized thermal shock (PTS) re-evaluation effort and the older Regulatory Guide 1.99, Revision 2 correlation. Even though the ASTM E 900-02 embrittlement correlation is a simplified version of the NRC model, a comparison of the two embrittlement correlation models utilizing the new database has proven to be revealing. Based on the new BWR data, both models are inadequate in their ability to predict BWR results; this inadequacy has even more significance for extrapolation outside of the database for BWR heat-up and cool-down curves, as well as some pressurized water reactor (PWR) heat-up curves. Other aspects of the two models, as revealed from this preliminary look at the new data, are presented.

Copyright © 2004 by ASME

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