Fatigue Crack Growth Testing of Sub-Clad Defects
Author:
Affiliation:
1. Bechtel Bettis, Inc., Bettis Atomic Power Laboratory, P.O. Box 79, ZAP 34E, West Mifflin, PA 15122-0079
Abstract
Publisher
ASME International
Subject
Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality
Link
http://asmedigitalcollection.asme.org/pressurevesseltech/article-pdf/121/3/269/5561884/269_1.pdf
Reference6 articles.
1. Wimunc E. A. , 1966, “How Serious Are Vessel Cladding Failures?,” Power Reactor Technology, Vol. 9, pp. 101–109.
2. Kondo T. , NakajimaH., and NagasakiR., 1971, “Metallographic Investigation on the Cladding Failure in the Pressure Vessel of a BWR,” Nuclear Engineering and Design, Vol. 16, North-Holland Publishing Co., pp. 205–222.
3. Canonico, D. A., 1977, “Significance of Reheat Cracks to the Integrity of Pressure Vessels for Light-Water Reactors,” ORNL/NUREG 15.
4. Vinckier, A. G., and Pense, A. W., 1974, “A Review of Underclad Cracking in Pressure Vessel Components,” WRC Bulletin 197, Aug.
5. Bernard J. L. , VagnerJ., Pellissier-TanonA., and FaureF., 1992, “Effect of Residual Stresses and Complex Loadings on the Fatigue Behavior of Underclad Cracks,” Nuclear Engineering and Design, Vol. 133, pp. 3–15.
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