Перегляд за автором "Breslavsky, D."

Сортувати за: Порядок: Результатів:

  • Effect of irradiation and thermo-induced processes on reactor in vessel elements during long-term operation 
    Breslavsky, D.; Tatarinova, O.; Kalchenko, O.; Tolstolutska, G. (Вопросы атомной науки и техники, 2022)
    A method for determining the effect of inhomogeneous temperature distribution, irradiation damage, irradiation swelling, irradiation creep of the material on the long-term strength of reactor in vessel internals and their ...
  • Stress-strain state and wear modelling for fuel rod – grid contact 
    Breslavsky, D.; Palamarchuk, P.; Tolstolutska, G.; Altenbach, H. (Problems of Atomic Science and Technology, 2023)
    The paper presents an approach for effective solution of the stress-strain state and wear prediction problem for the case of contact between fuel rod and grid surfaces of a nuclear reactor. Boundary-initial value elastic-plastic ...