Comparison of Маster curve with normative method of estimating WWER-1000 reactor pressure vessel metal fracture toughness за авторством V. M. Revka, L. I. Chyrko

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Different approaches to estimation of reactor pressure vessel material embrittlement за авторством V. M. Revka, L. I. Chyrko, Yu. V. Chaikovskiy, O. V. Trygubenko

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To the issue of accuracy of determination of irradiation embrittlement coefficient за авторством L. I. Chyrko, V. M. Revka, Yu. V. Chaikovskyi, M. H. Holiak, O. V. Tryhubenko, O. V. Shkapiak

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Weld metal irradiation embrittlement analysis in the range of over-design neutron fluences за авторством L. I. Chyrko, V. M. Revka, Yu. V. Chaikovskyi, M. H. Holiak, O. V. Tryhubenko, O. V. Shkapiak

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Radiation embrittlement of reactor pressure vessel materials of Rivne NPP unit 1 due to re-irradiation after recovery annealing за авторством M. H. Holiak, H. P. Hrynchenko, V. M. Revka, O. V. Tryhubenko, Yu. V. Chaikovskyi, L. I. Chyrko, O. V. Shkapiak

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