Results 91 to 100 of about 674,656 (134)

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, D Yu Erak
exaly   +2 more sources

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
core   +5 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
openaire   +1 more source

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
openaire   +1 more source

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
openaire   +1 more source

Hf COMPTON NEUTRON DETECTOR IN THE CORE OF WWER-1000

Problems of Atomic Science and Technology
Hafnium-based Compton self-powered detectors were investigated through MCNPX simulations of four fuel cycles in a WWER-1000 reactor core with fuel by “Westinghouse”. Seven detectors positioned at standard Rh detector locations were modeled to obtain: nuclide composition evolution, (n, γ)-reaction rates, neutron absorption rates, neutron and γ-ray flux ...
O. Ulybkin, V. Gann, P. Kuznietsov, O. Rybka, O. Pudov, V. Kutny, K. Kovtun   +6 more
openaire   +1 more source

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
openaire   +1 more source

SIMULATION OF TRANSIENT PROCESS ON WWER-1000 USING COUPLED APPROACH

POWER ENGINEERING: economics, technique, ecology
Research and modeling of thermohydraulic processes in NPP equipment is necessary for a deep and improved justification of reliable and safe operation of nuclear installations. Taking into account the accumulated experience and the latest technologies, the study of thermohydraulic processes is developing in the direction of applying innovative ...
Yurii Onyshchuk, Sergii Klevtsov
openaire   +3 more sources

Use of BEPU Technique for Analyses of BDBAs With Cooling in WWER-1000

Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 2009
Hypothetical conditions with deep cooling of coolant are analyzed for serial Reactor Installation (RI) with WWER-1000. The beyond design basis accident (BDBA) scenarios are specially chosen, to reveal the effectiveness of internal properties of nuclear fuel and reactor emergency protection (EP) in conditions when criterial parameters are close to the ...
Grigory L. Ponomarenko, Sergey B. Ryzhov, Mikhail A. Bykov, Aleksandr M. Moskalev   +3 more
openaire   +1 more source

WWER-1000 base metal reference steel and its characterisation

Nuclear Engineering and Design, 2005
The surveillance programmes of western power reactors include, in many cases, standard reference materials in addition to actual pressure vessel steels. These are specimens cut from standard steel plates (Heavy Section Steel Technology, JRQ, etc.) that are similar in composition and heat treatment to the base material in the respective reactor pressure
Beatriz Acosta, Luigi Debarberis, Soraia Pirfo, F. Sevini, A. Kryukov, A. Chernobaeva, F. Gillemot, M. Brumovsky   +7 more
openaire   +1 more source