Issue 36

T. Fekete, Frattura ed Integrità Strutturale, 36 (2016) 99-111; DOI: 10.3221/IGF-ESIS.36.10 111 [8] PNAE G-7-002-86: Equipment and pipelines strength analysis norms for nuclear power plants, (in Russian), Energoatomizdat, Moscow, (1990). [9] Schmitt, W., Keim, E., Linear elastic analysis of semi-elliptical axial surface cracks in a hollow cylinder, Int. J. Pres. Ves. Piping, 7 (1979) 105–118. [10] Szabolcs, G., Development of the PT-Shock program, Technical Report, VEIKI, Budapest, (1988). [11] Szabolcs, G., Fekete, T., The ACIB-RPV Code (in Hungarian), Technical Report, KFKI AEKI, Budapest, (1994). [12] Szabolcs, G., Fekete, T., Comparative Assesment of Results Produced by the ACIB-RPV Code and various Finite Element Codes (in Hungarian), Technical Report, KFKI AEKI, Budapest, (1994). [13] Szabolcs, G., Pesti, L., Fracture Mechanical Analysis of a VVER-440 Reactor Pressure Vessel in Case of a Circumferential Crack (in Hungarian), Technical Report, VEIKI, Budapest, (1987). [14] Trampus, P. (Editor), Pressurized Thermal Shock Analysis, Paks NPP Units 1-4, Technical Report, Paks, (2010). [15] Tuomisto, H., Thermal-Hydraulics of the Loviisa Reactor Pressure Vessel Overcooling Transients. Research Report (IVO-A-)1/87, IVO, Helsinki, (1987). [16] VERLIFE Guidelines for Integrity and Lifetime Assessment of Components and Piping in WWER Nuclear Power Plants – Version 2013. IAEA, Vienna, (to be published). [17] Westergaard, H.M., Bearing pressures and cracks, J. Appl. Mech, 61 (1939) A49–53.