Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments-Reference-Cited by-同舟云学术

Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments

Published:2003-11-01 Issue:4 Volume:125 Page:385-392
ISSN:0094-9930
Container-title:Journal of Pressure Vessel Technology
language:en
Short-container-title:

Author:

Eason Ernest D.¹,Nelson Edward E.¹,Heys Graham B.²

Affiliation:

1. Modeling and Computing Services LLC, 6560 Gunpark Drive, Suite B, Boulder, Colorado 80301 USA

2. H.M. Nuclear Installations Inspectorate, U.K. Health and Safety Executive, St Peters House, Balliol Road, Bootle, Merseyside, L20 3LZ, England

Abstract

Models of fatigue crack growth rates for medium and low sulfur ferritic pressure vessel steels in pressurized water reactor (PWR) primary environments are developed based on a recent collection of UK data and the EPRI Database for Environmentally Assisted Cracking (EDEAC). The combined UK and EDEAC database contains a broader range of experimental conditions specific to PWRs than either database by itself. Both probabilistic and conventional crack growth rate models are developed that reduce unnecessary conservatism for medium and low sulfur PWR primary water applications and eliminate the explicit dependence on rise time that caused difficulties applying prior models.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Link

http://asmedigitalcollection.asme.org/pressurevesseltech/article-pdf/125/4/385/5740734/385_1.pdf

Reference27 articles.

1. Eason, E. D., and Nelson, E. E., 1999, “Analysis of the UK Corrosion Fatigue Crack Growth Database,” Proprietary, Limited Distribution Report 990501, Modeling & Computing Services, Boulder, CO.

2. Eason, E. D., and Nelson, E. E., 1993, “Analysis of Fatigue Crack Growth Rate Data for A508 and A533 Steels in LWR Environments,” Report TR-102793, EPRI, Palo Alto, CA.

3. Eason, E. D., Nelson, E. E., and Gilman, J. D., 1998, “Modeling of Fatigue Crack Growth Rate for Ferritic Steels in Light Water Reactor Environments,” Nucl. Eng. Des., 184, pp. 89–111.

4. Eason, E. D., Nelson, E. E., and Gilman, J. D., 1995, “Technical Basis for a Revised Fatigue Crack Growth Rate Reference Curve for Ferritic Steels in Light Water Reactor Environments,” Weld. Res. Counc. Bull., 404, pp. 38–51.

5. Eason, E. D., Gilman, J. D., Jones, D. P., and Andrew, S. P., 1992, “Technical Basis for a Revised Fatigue Crack Growth Rate Curve for Ferritic Steels in Air,” ASME J. Pressure Vessel Technol., 114, pp. 80–86.