PSI - Issue 68

Vitalii Antonchenko et al. / Procedia Structural Integrity 68 (2025) 1305–1311 Vitalii Antonchenko et al./ Structural Integrity Procedia 00 (2025) 000–000

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References

S. Marie , S. Chapuliot, 2008, Improvement of the calculation of the stress intensity factors for underclad and through-clad defects in a reactor pressure vessel subjected to a pressurised thermal shock. International Journal of Pressure Vessels and Piping, 517– 531 Brumovsky, M., Martin, O, 2024, VERLIFE Guidelines for Integrity and Lifetime Assessment of Components and Piping in WWER Nuclear Power Plants, SOU NAEK 177:2023, Methodology for assessing brittle strength of WWER reactor pressure vessels IAEA-TECDOC-1627, Pressurized Thermal Shock in Nuclear Power Plants:Good Practices for Assessment IAEA-EBP-WWER-08, GUIDELINES ON PRESSURIZED THERMAL SHOCK ANALYSIS FOR WWER NUCLEAR POWER PLANTS