Аrticle received 13 December 2019For the prediction of irradiation embrittlement of reactor pressure vessel steels the analysis of surveillance data extracted from the IAEA International Database has been carried out. The dependences of the transition temperature shift on the neutron fluence corresponding to those acting on the vessel for 30–60 years of operation are evaluated. A proposal to increase the maximal value of neutron fluence on pressure vessel has been prepared to amend the regulatory and technical documents regarding the adjustment of the residual life of WWER-440 reactor.
Keywords: WWER, reactor pressure vessel, irradiation embrittlement, neutron fluence.
Article language: Russian. Pp. 3–14. DOI: 10.26277/SECNRS.2020.95.1.001.
