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AbstractAbstract
[en] The main activities concerning the state of art of WWER type pressure vessels included validation of empirical relationships between irradiation embrittlement and chemical composition as well as temperature, fluence and flux; validation of annealing regime; determination of initial mechanical properties and evaluation of actual material properties of the operating WWER-440/230 NPP pressure vessels. Concern tasks for life management of WWER-440 (models 230 and 231) and WWER 1000 were defined, based on the obtained results
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International Atomic Energy Agency, Vienna (Austria). International Working Group on Life Management of Nuclear Power Plants; 398 p; 1997; p. 23-41; IAEA specialists meeting on irradiation effects and mitigation; Vladimir (Russian Federation); 15-19 Sep 1997; Figs
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Report
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Conference
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