applied fracture mechanics

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Methodology for Pressurized Thermal Shock Analysis in Nuclear Power Plant 279[4] G. Geffraye et al., "CATHARE 2 V2.5_2: a Single Version for Various Applications,"[5] Proceeding of NURETH-13, Kanazawa City, Ishikawa Prefecture, Japan, Sept 27 th - Oct2 nd , 2009.[6] Barre, F. & Bestion, D. Validation of the CATHARE System Code for Nuclear ReactorThermalhydraulics, CEA STR/LML/EM/95-347, Grenoble, France, (1995).[7] IMS S.p.A. 1.4306 Reference Standard EN 10088.[8] IMS S.p.A. 1.4401 Reference Standard EN 10088.[9] J.C. Van Duysen, P. Todeschini, G. Zacharie. Effects of neutron irradiation attemperature below 500°C on the properties of cold worked 316 – a review. Effects ofRadiation on Materials: 17 th International Symposium, ASTM 1175 (1993) 747-776.[10] G.E. Lucas. The evolution of mechanical property change in irradiated austeniticstainless steels Journal of Nuclear Materials 206 (1993) 287-305.[11] G.E Lucas, M. Billone, J.E. Pawel, M.L. Hamilton. Implications of radiation-inducedreductions in ductility to the design of austenitic stainless steel structures. Journal ofNuclear Materials 233-237 (1996) 207-212.[12] P. Petrequin. Effect of irradiation on water reactor internals. AMES report n°11, COSUCT 94-074, June 1997, EUR 17694 EN.[13] Scott P. A review of irradiation assisted stress corrosion cracking. J Nucl Mater 1994,211:101.[14] C. Boyd, US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,THICKET 2008_Session-IX_Paper_29.pdf THICKET 2008 University of Pisa May 5-92008.[15] M. EricksonKirk, M. Junge, W. Arcieri, B.R. Bass, R. Beaton, D. Bessette, T.H.J. Chang, T.Dickson, C.D. Fletcher, A. Kolaczkowski, S. Malik, T. Mintz, C. Pugh, F. Simonen, N.Siu, D. Whitehead, P. Williams, R. S. Yin, NUREG-1806 Vol.1/Vol.2, “Technical Basis forRevision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10CFR 50.61)”, August 2007.[16] INTERNATIONAL ATOMIC ENERGY AGENCY, “Pressurized Thermal Shock inNuclear Power Plants: Good Practices for Assessment Deterministic Evaluation for theIntegrity of Reactor Pressure Vessel”, IAEA-TECDOC-1627, IAEA, Vienna (2010).[17] Araneo, D., “Procedura di analisi integrata di PTS per il RPV in un impianto nucleareWWER-1000/320 per mezzo dei codici accoppiati Relap5, Trio_U e Ansys”, F. D’Auria,M. Beghini, D. Mazzini, Pisa 2003.[18] L. Frustaci, “Analisi dello shock termico in un RPV tipo WWER1000 in condizioni diDEGB”, F. D’Auria, M. Beghini, D. Mazzini, Pisa 2005.[19] Myung Jo Jhung, Young Hwan Choi, Yoon Suk Chang1 and Jong Wook Kim2, Theeffect of postulated flaws on the structural integrity of RPV during PTS, NuclearEngineering and Technology, Vol.39 No.5 October 2007.[20] Bückner, H., A novel principle for the computation of stress intensity factors, ZAMM 50(1970), 529-546.
280Applied Fracture Mechanics[21] Rice, J.R., Some remarks on elastic crack-tip stress fields, Int. J. Solids and Structures8(1972), 751-758.[22] Fett T., Stress Intensity Factors T-Stresses Weight Functions, Schriftenreihe desInstitutsfürKeramikimMaschinenbau, IKM50, University of Karlsruhe 2008.
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PrefaceKnowledge accumulated in the
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Section 1Computational Methods of F
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Fracture Mechanics Based Models of
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