Перегляд за автором "Azarenkov, M.O."

Сортувати за: Порядок: Результатів:

  • Contribution of radionuclides to heat release in the process of SNF dry storage 
    Rudychev, V.G.; Azarenkov, M.O.; Girka, I.O.; Rudychev, Y.V.; Shchus, O.P. (Вопросы атомной науки и техники, 2017)
    In the paper the radionuclide contribution to heat release at dry storage of spent nuclear fuel (SNF) of WWER-1000 was researched. β- and γ-radiation from 60 of the most active fission products, and α-radiation from 20 ...
  • Efficiency of combined Fe and Pb radiation shield of transport casks for SNF transportation 
    Rudychev, V.G.; Azarenkov, M.O.; Girka, I.O.; Rudychev, Y.V. (Вопросы атомной науки и техники, 2022)
    The possibility of increasing the efficiency of combined iron and lead shielding of transport containers (TC) for SNF transportation by railroad is studied. Models for the transport of SNF γ-quanta are developed, that make ...
  • Optimization of bremsstrahlung characteristics for irradiating thick objects 
    Rudychev, V.G.; Azarenkov, M.O.; Girka, I.O.; Rudychev, Y.V. (Вопросы атомной науки и техники, 2022)
    The characteristics of bremsstrahlung (BS) irradiated at different angles from a three-layer converter made of Ta, water, and Fe, the electron energy is 7.5 MeV, was investigated. It is shown that Ta thickness increasing ...
  • Optimization of the bremsstrahlung converter 
    Rudychev, V.G.; Azarenkov, M.O.; Girka, I.O.; Lazurik, V.T.; Rudychev, Y.V. (Вопросы атомной науки и техники, 2022)
    Variants of the formation of bremsstrahlung (BS) distributions along an extended converter, which ensures the maximum thickness of an object under two-sided and four-sided irradiation, are studied. For the target of the ...
  • The efficiency of radiation shielding made from materials with high atomic number and low mass density 
    Rudychev, V.G.; Azarenkov, M.O.; Girka, I.O.; Rudychev, Y.V. (Вопросы атомной науки и техники, 2021)
    The radiation shielding from γ-quanta of the existing transport containers (TC) for transportation of spent nuclear fuel (SNF) is made of steel or steel plus Pb 25…30 cm thick and weighting ⁓ 60…80 t. The application of ...