Перегляд за автором "Kryukov, A."

Сортувати за: Порядок: Результатів:

  • Prediction of irradiation embrittlement in WWER-440 Reactor Pressure Vessel materials 
    Brumovsky, M.; Kytka, M.; Debarberis, L.; Gillemot, F.; Kryukov, A.; Valo, M. (Вопросы атомной науки и техники, 2007)
    Prediction of irradiation embrittlement of Reactor Pressure Vessel (RPV) materials is performed usually in accordance with relevant codes and standards that are based on large amount of information from surveillance and ...
  • Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE 
    Debarberis, L.; Sevini, F.; Acosta, B.; Pirfo, S.; Bieth, M.; Weisshaeupl, H.; Törrönen, K.; Kryukov, A.; Valo, M. (Проблемы прочности, 2004)
    Radiation embrittlement and aging mechanisms for NPP reactor pressure vessels and vessel internals have been studied within NPP Plant Life Management (PLIM) for evaluation, prediction, and monitoring of the critical ...
  • Use of a Semi-Mechanistic Analytical Model to Analyze Radiation Embrittlement of Model Alloys: Cu and P Effects 
    Debarberis, L.; Kryukov, A.; Gillemot, F.; Valo, M.; Morozov, A.; Brumovsky, M.; Acosta, B.; Sevini, F. (Проблемы прочности, 2004)
    We performed analysis of the basic mechanism of radiation embrittlement of steels and weld seams with account of the direct matrix fracture, precipitation and segregation of chemical elements. A model is proposed, which ...