1. General knowledge

Corrosion product transport and fouling in nuclear steam generators

Optimisation of non-destructive testing

Using probabilistic methods for solving the problem of ensuring leak tightness of heat exchanger tubes of nuclear power plant steam generators

Failure analysis and prevention in SCC and corrosion fatigue cases

Probabilistic ageing and risk analysis tools for nuclear piping

Integrity assessment for safety relevant nuclear piping

Design basis and design features of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia). Report of the IAEA technical co-operation project RER/9/004 on evaluation of safety aspects of WWER-440 model 213 nuclear power plants

Fatigue life prediction of pipeline with equivalent initial flaw size using Bayesian inference method

IAEA Releases 2019 Data on Nuclear Power Plants Operating Experience

Recent Developments in Irradiation-Resistant Steels

Embrittlement of nuclear reactor pressure vessels

On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels

Irradiation hardening and materials embrittlement in light water reactor (LWR) environments

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