Results 71 to 80 of about 186 (119)

Stresses and Strains of Equipment Inside a WWER-1000 Nuclear Reactor

Biuletyn Instytutu Spawalnictwa, 2016
O.W. Machnienko, I.W. Mirzov
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PRINCIPLES OF WATER SUPPLY REGULATION OF THE WWER-1000 STEAM GENERATOR

Young Scientist, 2020
Mykhailo Yarotskyi, Oleksandr Brunetkin
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Development Of A Neutronic Model Of The Wwer-1000 Reactor Facility Core

Eurasian Journal of Physics and Functional Materials
D.M. Seken, A.S. Surayev, R.A. Irkimbekov, G.A. Vityuk, N.Y. Mukhamedov, O.M. Zhanbolatov, V.A. Vityuk   +6 more
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Analysis of embrittlement of WWER-1000 RPV materials

International Journal of Pressure Vessels and Piping, 2012
Abstract Analysis of embrittlement for WWER-1000 RPV materials is performed on the basis of available and original experimental data. Contributions of thermal aging and neutron irradiation to embrittlement are considered for base and weld metals. Equations have been obtained for the shift of the critical temperature of brittleness as a function of ...
B Z Margolin
exaly   +2 more sources

Probability of Rupture for WWER-1000 Main Piping

Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, 2020
Abstract A probability of rupture for WWER-1000 main piping was calculated based on the Failure Assessment Diagram (FAD), treating material properties of welds (the most likely zone for crack growing and its nucleation) and crack morphology parameters as stochastic values.
Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov   +3 more
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Assessment of the WWER-1000 reactor condition

International Journal of Pressure Vessels and Piping, 2006
The current state of the materials (steel, welds, anticorrosive cladding metal) of WWER-1000 RPVs has been examined, taking into consideration special features of their manufacture and operation for 30 years. The possibility of operating these reactors after their design service life has been estimated, allowing for the degradation of properties due to
B.T. Timofeev, G.P. Karzov
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Basic results of the Russian WWER-1000 surveillance program

Nuclear Engineering and Design, 1997
The surveillance test results of the reactor pressure vessels (RPV) of three Russian WWER-1000 type units designated Units 1, 2 and 3 are given and the embrittlement rates compared to those predicted by the Russian Regulatory Guide. The surveillance materials properties measured by manufacturers of the RPVs are reviewed.
Kryukov, A., Nikolaev, Yu.A., Planman, Tapio, Platonov, P.   +4 more
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Development of alternative fuel assembly for WWER-1000 reactor

Nuclear Engineering and Design, 1997
Abstract An alternative design of fuel assembly has been developed for the WWER-1000 reactor with the aim of assuring a geometrical stability of the core during operation. The fuel assembly provides enhanced safety and substantial improvement in the WWER-1000 fuel cycle economics.
Mikhail I. Solonin, Yuri K. Bibilashvili, Nikolai B. Sokolov, Albert K. Panyushkin, Vladimir Tsibulia, Oleg B. Samoylov, Vadim B. Kurilev, Vladimir S. Kuul, Vladimir S. Kuul, Viktor B. Kaidalov, Rudolf A. Peskov, Valentin F. Ershov   +11 more
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Results of measuring the residual strains in the WWER-1000 reactor vessel

Physics of the Solid State, 2010
Internal stresses in specimens cut from the natural WWER-1000 reactor vessel have been investigated using neutron diffraction. Thin and thick templates (flat specimens cut from a bulk product) have been studied and the effect of the volume factor on the stress distribution has been revealed.
V. V. Sumin, S. G. Sheverev, R. Schneider, R. Wimpory, A. M. Balagurov   +4 more
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