Zobrazeno 1 - 10
of 49
pro vyhledávání: '"I. I. Fedik"'
Publikováno v:
Atomic Energy. 120:361-365
Autor:
I. I. Fedik, L. I. Mironova
Publikováno v:
Journal of Machinery Manufacture and Reliability. 44:720-725
A mathematical model of the determination of thermal stresses in the case of local thermal loading of two intersecting cylindrical rotational shells with a variable wall thickness is given. The suggested model can be taken as a rough estimate of ther
Autor:
N. M. Vlasov, I. I. Fedik
Publikováno v:
Journal of Thermal Stresses. 32:755-767
Internal stresses occur within a material in the presence of non-uniform deformation. The main types of the internal stresses are thermal, residual and those due to structural defects. These stresses affect diffusion (of interstitial impurities such
Autor:
P. M. Gavrilov, N. A. Piskunova, I. I. Fedik, A. M. Dmitriev, N. N. Khrennikov, V. I. Nalivaev, V. P. Deniskin
Publikováno v:
Atomic Energy. 103:675-680
The salient features of using a solid substance to cool the core of a nuclear reactor and the associated advantages and limitations are examined. Conceptual proposals concerning the core design and the arrangement of the in-reactor space of a high-te
Publikováno v:
International Journal of Hydrogen Energy. 31:167-170
Application of hydrogen is a necessary condition to achieve acceptable power and overall-dimensional characteristics of space power and propulsion plants. Some functional elements as part of the plants require protection from hydrogen, which is provi
Publikováno v:
Atomic Energy. 99:792-798
A validation of the possibility of developing and the basic advantages of a high-temperature nuclear reactor where the first-loop coolant is a solid are presented. The basic requirements for a solid coolant are formulated, a technology for fabricatin
Autor:
E. M. Rakitskaya, A. A. Yastrebkov, A. S. Gontar, M. V. Nelidov, Yu. V. Nikolaev, I. I. Fedik
Publikováno v:
Atomic Energy. 99:799-805
The characteristic properties of hardened single-crystal alloys (Mo-Nb, W-Nb, W-Ta) and UO2-x with open thermally stabilized porosity are presented. The combination of the indicated materials makes thermionic fuel elements very stable with a long ser
Autor:
A. M. Nikolotov, B. A. Gabaraev, Yu. I. Mityaev, V. P. Deniskin, V. K. Vikulov, F. E. Ermoshin, I. I. Fedik, M. I. Rozhdestvenskii, V. I. Nalivaev, S. S. Gavrilin, A. A. Romenkov
Publikováno v:
Atomic Energy. 98:233-241
The concept of a direct-flow channel reactor with supercritical-pressure water (CR-SCP) is presented. Neutron-physics, thermohydraulic, and strength calculations are used to substantiate the fundamental core design with a heavy-metal moderator which
Autor:
I. I. Fedik, V. P. Smetannikov, V. K. Ulasevich, V. M. Talyzin, Yu. S. Cherepnin, Sh. T. Tukhvatulin, V. A. Pavshuk, V. P. Deniskin, E. K. D’yakov, N. N. Ponomarev-Stepnoi
Publikováno v:
Atomic Energy. 98:151-157
The history of the development of the first domestic high-temperature gas-cooled reactor — a unique experimental reactor for testing the core of reactors for nuclear-powered rocket motors — is briefly reviewed. The extraordinary requirements whic
Autor:
G. V. Konyukhov, A. I. Petrov, S. A. Popov, V. S. Rachuk, A. I. Belogurov, Yu. I. Mamontov, I. I. Fedik, E. K. D?yakov, I. A. Mogil?nyi, V. A. Konovalov, F. P. Raskach, I. I. Zakharkin
Publikováno v:
Atomic Energy. 97:604-607