An updated correlation for crack-arrest fracture toughness for nuclear reactor pressure vessel steels |
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| Affiliation: | 1. Department of Chemistry and Bioengineering, Faculty of Engineering, Iwate University, 4-3-5 Ueta, Morioka, Iwate 020-8551, Japan;2. Chemical Technology Laboratory, Taiho Pharmaceutical Co., Ltd., 200-22 Motohara, Kamikawa-machi, Kodama-gun, Saitama 367-0241, Japan;1. School of Science, Xi’an University of Science & Technology, No. 58 Yanta Middle Road, Xi’an 710054, PR China;2. School of Mechanical Engineering, Xi’an University of Science & Technology, No. 58 Yanta Middle Road, Xi’an 710054, PR China;1. Sama Technical and Vocational Training College, Islamic Azad University, Roudehen Branch, Roudehen, Iran;2. Physics Department, Islamic Azad University , North Tehran Branch, Tehran, Iran;1. Scuola di Scienze e Tecnologie, Universit Camerino, Via madonna delle carceri 9, 62032, Camerino, Italy;2. Istituto Nazionale di Ricerca Metrologica, INRiM, Strada delle Cacce 91, 10135, Torino, Italy;3. IM2NP-UMR CNRS Aix Universit Marseille, Avenue Escadrille Normandie Niemen - Case 142 - 13397 Marseille Cedex 20, Marseille, France;4. INFN, Sezione di Perugia, Via A. Pascoli, 06123, Perugia, Italy |
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| Abstract: | An updated and statistically-rigorous correlation is provided for crack-arrest toughness values versus normalized temperature for light-water nuclear reactor pressure vessel (RPV) steels. The database used in this effort is larger than applied heretofore and includes results from tests of laboratory-size specimens and from tests of large-scale specimens, which contain features prototypical of operating RPVs. The mathematical methodology used is based on a lognormal distribution, with its parameters calculated by orthogonal distance regression. This correlation was developed as one of several items updated for use in the US Nuclear Regulatory Commission's extensive program to evaluate and potentially revise its rule for ensuring structural integrity of operating RPVs when subjected to pressurized thermal-shock transients. |
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