Abstract
An additional assessment and analysis of the degree of radiation embrittlement of the materials used in the VVER-1000 vessels of nuclear power plants in Ukraine are performed according to the standard (regular) program of irradiation and investigation of control samples. New results for samples tested for impact toughness are presented and compared with the results obtained using reconstitutive procedures. It is shown that the results of control-sample tests performed according to the standard program (with a fluence deviation of ±15% above the norm in a group of 12 samples) can be used to assess the state of the material and preliminary substantiation of the serviceability of vessels before obtaining more accurate data on embrittlement using reconstituted samples.
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