Zobrazeno 1 - 10
of 89
pro vyhledávání: '"VVER-1000 reactor"'
Autor:
L. I. Chyrko, V. M. Revka, Yu. V. Chaikovskyi, M. G. Goliak, O. V. Trygubenko, O. V. Shkapyak
Publikováno v:
Âderna Fìzika ta Energetika, Vol 21, Iss 4, Pp 323-327 (2020)
The comparison of experimental values of the critical brittle temperature ΔTF and reference temperature ΔT0 of VVER-1000 reactor vessel weld metal with an elevated content of manganese and nickel is performed. ΔTF and ΔT0 values are defined proce
Externí odkaz:
https://doaj.org/article/3a403d6cdb4c46f3873ded4f9e79a8ad
Publikováno v:
مجله علوم و فنون هستهای, Vol 41, Iss 1, Pp 40-49 (2020)
The loss of coolant accident is due to the reduction of the coolant fluid volume in the first circuit. The direct cause of this accident is the mechanical failure or fatigue in the material of the first circuit components during the power plant opera
Externí odkaz:
https://doaj.org/article/9cdcd112186d4c40b796bb6d93c72045
Autor:
Yu. S. Gulchuk, L. I. Chyrko
Publikováno v:
Âderna Fìzika ta Energetika, Vol 20, Iss 3, Pp 243-247 (2019)
The paper presents the procedure developed at the Department of Radiation Material Science of INR NAS of Ukraine for longitudinal radiometric scanning of surveillance specimens of the Ukrainian reactor vessels and its joint application with macrostru
Externí odkaz:
https://doaj.org/article/139f8f33534d443c8c6f84da44b01c6d
Publikováno v:
Trudy Odesskogo Politehničeskogo Universiteta, Vol 1, Iss 54, Pp 46-50 (2018)
An automated system for control of VVER-1000 reactor fuel properties considering fuel element cladding damage parameter, fuel burnup and axial offset has been proposed. Using the synergic method for control of nuclear fuel properties (CET-method) opt
Externí odkaz:
https://doaj.org/article/a3ed9981f2704d62bbb8db65a48d1f6e
Akademický článek
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Akademický článek
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Publikováno v:
Âderna Fìzika ta Energetika, Vol 16, Iss 2, Pp 144-151 (2015)
Investigations to determine the influences of geometrical parameters of the calculational VVER-1000 reactor model to the results of internal irradiation condition determination are carried out. It is shown that the values of appropriate sensitivity m
Externí odkaz:
https://doaj.org/article/011b361503394b8ab179b77a366862a4
Publikováno v:
Nukleonika, Vol 59, Iss 2, Pp 67-72 (2014)
One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors. In this paper, we developed
Externí odkaz:
https://doaj.org/article/ec7c0cdabc8d45edb3fc57884be089d7
Publikováno v:
Âderna Fìzika ta Energetika, Vol 21, Iss 4, Pp 323-327 (2020)
The comparison of experimental values of the critical brittle temperature ΔTF and reference temperature ΔT0 of VVER-1000 reactor vessel weld metal with an elevated content of manganese and nickel is performed. ΔTF and ΔT0 values are defined proce
Publikováno v:
Mechanics and Advanced Technologies; Том 5 № 2 (2021)
Mechanics and Advanced Technologies; Vol. 5 No. 2 (2021)
Mechanics and Advanced Technologies; Vol. 5 No. 2 (2021)
Background. Improvement of the methodology for the computational analysis of residual stresses in the structural elements of the reactor is an integral part of the work when extending the service life of NPP power units. Objective. Determine the valu