Перегляд за автором "Kytka, M."

Сортувати за: Порядок: Результатів:

  • Integrated Surveillance Specimen Program for WWER-1000/V-320 Reactor Pressure Vessels 
    Brumovský, M.; Brynda, J.; Kytka, M.; Novosad, P.; Žďárek, J. (Вопросы атомной науки и техники, 2007)
    Surveillance specimen programs play an important role in reactor pressure vessel lifetime assessment as they should monitor changes in pressure vessel materials, mainly their irradiation embrittlement. Standard surveillance ...
  • Mechanisms of Fracture in Neutron-Irradiated 15Ch2MFA Steel 
    Valek, S.; Hausild, P.; Kytka, M. (Проблемы прочности, 2008)
    The influence of irradiation on fracture properties of 15Ch2MFA pressure vessel steel is studied. The distribution of inclusions and carbides is characterized. The quantitative fractography of broken Charpy specimens is ...
  • 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 ...