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CitationsCitations0ReferencesReferences0Article · Aug 2001 Article · Nov 1991 Article · Feb 1973 Data provided are for informational purposes only. Although carefully collected, accuracy cannot be guaranteed. Publisher conditions are provided by RoMEO. Differing provisions from the publisher's actual policy or licence agreement may be applicable.This publication is from a journal that may support self archiving.AbstractThe B&W Owners Group submitted justification for resetting the initial RTNDT for the Linde 80 weld materials using ASME Code Case N-629/N-631 to the US Nuclear Regulatory Commission and received the NRC Safety Evaluation Report with some adjustments. Two major issues were encountered during the review and approval process: 1) The pressurized thermal shock experiment data from Oak Ridge National Laboratory with full-length axial (very long) cracks fall below the Code Case curve. This observation led to the question whether there are implicit crack size limitations in the code case, and 2) For the large populations of data examined, a larger portion of data falls below the Code Case N-629/N-631 curve than the ASME KIC curve, prompting a question whether the code case is functionally equivalent to the ASME KIC curve. This paper describes these major issues and how they were addressed.Do you want to read the rest of this conference paper?
CitationsCitations0ReferencesReferences0Conference PaperJanuary 2002The ASME Boiler and Pressure Vessel Code provides fracture toughness curves of ferritic pressure vessel steels that are indexed by a reference temperature for nil ductility transition (RTNDT ). The ASME Code also prescribes how to determine RTNDT . The B&W Owners Group has reactor pressure vessels that were fabricated by Babcock & Wilcox using Linde 80 flux. These vessels have welds called... ArticleJanuary 2004 · Journal of ASTM InternationalThe Babcock & Wilcox Company used Mn-Mo-Ni automatic submerged-arc welds with the Linde 80 flux type for the fabrication of 14 currently operating PWR reactor vessels. Due to the fact that the weld wire was copper-coated (high copper content) and that they have low upper-shelf toughness properties, the welds are limiting with respect to pressurized thermal shock analysis. The welds (reactor... Conference PaperJanuary 2003It has long been recognized that there is a considerable difference between the dynamic and quasi-static fracture toughness reference temperature. However, it has not been clear whether this loading rate effect extends into the quasistatic loading regime. The current fracture toughness reference temperature test standard for ferritic steels (ASTM E1921) specifies an allowable quasi-static... ArticleJanuary 2000The Japanese KIR Committee conducted a large scale fracture toughness testing program for Japanese pressure vessel steels. The fracture toughness data, which has been analyzed in this paper, was developed under the KIR Project. Previous publications of the results from this program concluded that this database is conservatively lower bounded by the existing ASME Boiler and Pressure Vessel Code... Data provided are for informational purposes only. Although carefully collected, accuracy cannot be guaranteed. Publisher conditions are provided by RoMEO. Differing provisions from the publisher's actual policy or licence agreement may be applicable.This publication is from a journal that may support self archiving.}