[en] Chemically aggressive high-temperature liquid fuels and/or coolants are considered in various prospective designs of fast and epithermal nuclear systems like Lead-Cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), or Supercritical Water-Cooled Reactor (SCWR). The corrosion resistance of structural materials and, specifically, the long-term combined (n,γ)-irradiation impacts on their composition and mechanical properties at interfaces with corrosion agents becomes a key issue of material selection currently aggravated with the lack of full-scale reactor irradiation tests. In this paper, we summarize the NSC KIPT developed methodology and present the selected results of simulation experiments on corrosion behaviour of MSR candidate materials, the KIPT designed Hastelloy^TM type Ni-based alloys A and B that differ only by the presence (in alloy B) of minor dopants of Nb and Y. The specimens of alloys A and B embedded into the NaF-ZrF₄ melt (660 deg. C) were irradiated by 10MeV e-beam at the KIPT located Electron Irradiation Test Facility (EITF). It was designed to provide an entirely controllable irradiation environment - the target temperature, e-beam spectrum and irradiation load of melt and specimens. The latter issue (prediction of dose and damage rates in EITF and their scalability to the target MSR irradiation environment) has been resolved by means of extensive Monte Carlo (MC) computer simulation of EITF (e,γ)-experiment and MSR (n,γ)-environment using the same CERN Geant4 Toolkit based MC code RaT 3.0 with the G4NDL3.8 neutron data library. Similar to MCNPX, this in-house developed code is capable of consistent MC modelling of electromagnetic and hadronic (incl. neutrons and fission fragments) interactions peculiar to EITF and MSR irradiation of fuel and structural materials. The MC simulation results show that though (e,γ)-beams are not well suitable to simulate bulk effects of reactor neutron damage, they are feasible to activate corrosion at interfaces since it is mainly affected by nuclear heating scaled by the specific deposited energy E_dep (or absorbed dose) that speeds up chemical reactions and enhances diffusion. The nuclear heating rates obtained in the EITF (e,γ)-beam experiment are fairly consistent with those expected within various scenarios of construction materials irradiation in MSRs by neutrons, γ-quanta and, optionally, by fission fragments of molten salt based fuel mixes. Owing to the specific design of the EITF target container assembly (CA), the energies E_dep deposited at various interfaces of alloy with melt differed by ∼51 times ranging from 121 up to 6192eV per autom at the same 700hrs long e-irradiation. The measurements of e-irradiation enhanced corrosion rates of 0.5wt%Nb and 0.05wt%Y doped alloy B has revealed precisely the same ratio that is the evidence of the proportionality of an irradiation effect to an absorbed dose. No such a simple scaling was observed for the reference (undoped) alloy A that is characterised by substantially lower threshold of e-irradiation impact on corrosion resistance. Our MC calculations argue that the presence of these minor dopants has no noticeable effect on the EITF e-beam interaction with targets as well as on the nuclear responses of alloys under consideration. Thus we discuss possible explanations of the substantial impact of minor dopants on corrosion behaviour from the point of view of the theoretical consideration of corrosion kinetics in liquid metal and fluoride melts. We also announce the planned extensions of the NSC KIPT EITF experimental setup directed toward the simulation experiments using convection loops. They are intended for LFR and SCWR related applications to provide the investigation of irradiation impact on corrosion resistance of topical construction materials