Results 161 to 170 of about 3,636 (213)

Extended analysis of VVER-1000 surveillance data

International Journal of Pressure Vessels and Piping, 2002
Abstract Up to now 20 surveillance specimen sets of 14 VVER-1000 Reactor Pressure Vessel (RPV) have been evaluated in Russia, Ukraine and Bulgaria by different testing organisations: • Kurchatov Institute, Russia (10 RPVs); • Institute for Nuclear Research, Ukraine (two RPVs); • Institute of Metal Science, Bulgaria (two RPVs).
Aleksander M Kryukov
exaly   +2 more sources

Subchannel analysis of nanofluids application to VVER-1000 reactor

Chemical Engineering Research and Design, 2013
Abstract In this study a thermal-hydraulic analysis is performed of nanofluids as a coolants in subchannels in hot fuel assembly of VVER-1000 reactor by subchannel method. Water-based nanofluids containing various volume fractions of Al2O3 nanoparticles are analyzed.
Ehsan Zarifi, Gholamreza, Farzad Veysi
exaly   +2 more sources

Validation of a VVER 1000 Trace Model

Proceedings of the Bulgarian Academy of Sciences, 2022
The presented article discusses developing and validation of a VVER 1000 TRACE V5.0p5 model. Developing such model for a TRACE computer code is important as it increases the capability of the analyses in simulating nuclear power plant behaviour for different accidents including capabilities for simulating 3D thermal hydraulic phenomena in the reactor ...
Groudev, Pavlin, Vryashkova, Petya, Stefanova, Antoaneta, Georgiev, Valentin   +3 more
openaire   +1 more source

Temperature regulation and maneuverability of VVER-1000

Atomic Energy, 2011
The possibility of using coolant temperature changes (temperature regulation) as an additional control on energy release in the core of VVER-1000 reactors is examined. It is shown that it is desirable to use temperature regulation in maneuvering regimes of a power-generating unit of a nuclear power plant.
S. P. Averyanova, A. A. Dubov, K. B. Kosourov, P. E. Filimonov   +3 more
openaire   +1 more source

30th anniversary of VVER-1000 startup

Atomic Energy, 2010
The first power-generating unit with VVER-1000 was brought on line at the Novovoronezh nuclear power plant on May 30, 1980. The history of VVER-1000 development is briefly recounted. The possible goals and paths for further development of light-water vessel reactor construction in nuclear power in Russia are briefly examined.
V. G. Asmolov, Yu. M. Semchenkov, V. A. Sidorenko   +2 more
openaire   +1 more source

"Full-Core" VVER-1000 calculation benchmark

Kerntechnik, 2020
Abstract This work deals with the \Full-Core" VVER-1000 calculation benchmark which was proposed on the 26th Symposium of AER [1]. Recently, the calculation benchmarks \Full-Core" VVER-440 [2] and its extension [3] have been introduced in the AER community with positive response [4, 5].
Sprinzl, D., Krysl, V., Mikolas, P., Zavorka, J., Timr, J., Bilodid, Y., Temesvari, E., Pos, I., Kalinin, Y., Shcherenko, A., Aleshin, S., Bahadir, T.   +11 more
openaire   +3 more sources

Modernization of Existing VVER-1000 Surveillance Programs

Journal of ASTM International, 2012
Abstract According to generally accepted world practice, evaluation of the reactor pressure vessel (RPV) material behavior during operation is carried out using tests of surveillance specimens. The main objective of the surveillance program consists in insurance of safe RPV operation during the design lifetime and lifetime-extension ...
V. Kochkin, D. Erak, D. Makhotin
openaire   +1 more source

Seismic Analysis of VVER-1000 Polar Crane

Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, 2021
Abstract This article discuss an analytical dynamic model of a polar crane to assess its seismic strength based on artificially generated accelerograms. The polar crane is installed under the dome of the VVER-1000 NPP containment and serves to move various cargoes in the reactor compartment, including nuclear hazardous cargo.
Yaroslav Dubyk, Vitalii Antonchenko
openaire   +1 more source

Calculation of “full core” VVER-1000 benchmark

Kerntechnik, 2018
Abstract The 2-D benchmark related to the “full-core” of VVER-1000 was proposed at the AER working group A&B meeting in 2015. Such type of benchmarks requires the adequate specification of the volume surrounding the core where geometry is complex enough.
S. S. Aleshin, A. S. Bikeev, D. S. Oleynik, A. I. Shcherenko   +3 more
openaire   +1 more source

Enhanced VVER-1000 Fuel Technology and Performance

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
The United States Department of Energy, through the Pacific Northwest National Laboratory (PNNL), provides management and technical support for the International Nuclear Safety Program (INSP) to improve the safety level of VVER-1000 nuclear power plants in Central and Eastern Europe.
H. Shah, R. Latorre, G. Raspopin, J. Sparrow   +3 more
openaire   +1 more source