Investigation of Processes Brittle Materials Housing Components of Nuclear Reactors, Depending on the Intensity of the Radiation

Annotation The aim is to analyze the effect of fast neutron flux density change in the critical transition temperature of the metal weld VVER-1000 housing. Work carried out in the Laboratory of Neutron Dosimetry Institute of Reactor Materials and Technology Research Center "Kurchatov Institute". The paper presents: Literature review on irradiation embrittlement of materials VVER-1000 reactors. Test procedures for impact bending samples and determine the value of the critical brittleness temperature Tk The results of mathematical processing of the experimental data on radiation of the weld metal embrittlement of VVER-1000 reactors. In its search for mathematical models that adequately describe the change in mechanical properties of metal, evaluated their possible extrapolation to predict the kinetics of radiation embrittlement of the metal housing. Analyzed data sets on irradiation embrittlement of the weld metal specimens irradiated program witnesses samples and research programs. It is shown that the radiation embrittlement of the reactor pressure vessel weld metal VVER-1000 describes the different models, depending on the concentration of nickel. The procedure of application of the experimental data obtained after accelerated irradiation, allowing the use of these data for modeling and evaluating the kinetics of radiation embrittlement of the weld metal VVER-1000 reactors. The work includes: 85 pages, 40 figures, 18 tables, the Bible. 19 titles. Keywords: VVER-1000, radiation embrittlement of the reactor building, the critical temperature of brittleness.