Results 11 to 20 of about 4,383 (200)

Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility [PDF]

Science and Technology of Nuclear Installations, 2012
The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000.
A. Del Nevo, M. Adorni, F. D'Auria, O. I. Melikhov, I. V. Elkin, V. I. Schekoldin, M. O. Zakutaev, S. I. Zaitsev, M. Benčík   +8 more
doaj   +6 more sources

Accident Management in VVER-1000 [PDF]

Science and Technology of Nuclear Installations, 2008
The present paper deals with the investigation study on accident management in VVER-1000 reactor type conducted in the framework of a European Commission funded project. The mentioned study involved both experimental and computational fields. The purpose of this paper is to summarize the main findings from the execution of a wide-range analysis focused
D'AURIA, FRANCESCO SAVERIO, SUSLOV A, MUELLNER N, PETRANGELI G, CHERUBINI M.   +4 more
core   +7 more sources

Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors

WWER Fuel Performance, Modelling and Experimental Support, 2015
FINIX is a recently developed fuel behaviour module that is designed to provide "simple but sufficient" descriptions of the most essential fuel behaviour phenomena in multiphysics simulations. In such simulations, it is possible to obtain significant improvement in the feedback to neutronics or thermal hydraulics modelling even with a relatively simple
Valtavirta, Ville, Kättö, Joonas, Loukusa, Henri, Ikonen, Timo, Leppänen, Jaakko, Tulkki, Ville, Syrjälahti, Elina   +7 more
core   +8 more sources

Possible in-service damages of steam generators at VVER-1000 and VVER-1200 NPP units and their impact on long-term operation [PDF]

E3S Web of Conferences, 2020
Specific features of corrosion-mechanical damages of primary circuit header to steam generator vessel branch welds at VVER-1000 NPPs and their impact on safety and economic efficiency during long-term operation are analysed. Measures to avoid the damages
Arzhaev Alexander, Arzhaev Alexey, Makhanev Valentin, Antonov Mikhail, Emelianov Anton, Kalyutik Aleksander, Karyakin Yury, Kurakin Maksim, Lyashenko Daniil, Arzhaev Kirill, Denisov Ilya   +10 more
doaj   +2 more sources

Improving the accuracy of thermal power determination of VVER

Ядерна фізика та енергетика, 2019
In most algorithms for forming control signals, locks and protection of VVER, the value of the reactor’s thermal power (RTP) is used. This article is dedicated to the analysis of the problem of determining the RTP of VVER-1000.
V. I. Borysenko, D. V. Budyk, V. V. Goranchuk   +2 more
doaj   +2 more sources

Advanced process simulation with APROS for VVER-91, the next generation reactor design for VVER-1000

, 1997
The paper describes the capabilities of APROS code in the simulation of the VVER-91 concept. The VVER-91 models realized with APROS are described and a short overview of the various types of analysis performed is given. Particular emphasis is paid on the ATWS analyses performed with APROS.
Norrman, Sixten, Kyrki-Rajamäki, Riitta, Siltanen, Pertti, Porkholm, Kari, Latyeva, L., Semishin, V., Kalugin, Sergei, Puska, Eija-Karita   +8 more
core   +8 more sources

A method for VVER fuel element cladding reliability prediction [PDF]

Ядерна фізика та енергетика, 2014
Considering a VVER-1000 fuel assembly averaged fuel element (FE), based on the accepted FE cladding damage limit value, the FE cladding failure probability was determined, thus the possibility of this reliability pre-diction by means of controlling the ...
S. M. Pelykh, M. V. Maksimov, M. V. Nikolsky   +2 more
doaj   +1 more source

Estimation of material degradation of VVER-1000 baffle [PDF]

EPJ Web of Conferences, 2017
The planned lifetime of the first commercial VVER-1000 units were designed for 30 to 35 years. Most of the early VVER plants are now reaching and/or passing the 35-year mark.
Harutyunyan Davit, Košál Michal, Vandlík Stanislav, Hojná Anna, Schulc Martin, Flibor Stanislav   +5 more
doaj   +3 more sources

Calculation of radiation fields in the VVER-1000 concrete biological shield using Monte Carlo code Serpent [PDF]

Ядерна фізика та енергетика, 2023
To calculate radiation fields in the concrete biological shield (CBS) of the VVER-1000 reactor in this work, we have developed and applied the Monte Carlo code Serpent simulation framework based on the variance reduction technique. We have quantified the
O. M. Khotiaintseva, O. R. Trofymenko, V. M. Khotiaintsev, A. V. Nosovskyi, S. E. Sholomytsky, V. I. Gulik   +5 more
doaj   +1 more source

The problem of minimizing the radioactive leakage into the VVER circuit under normal conditions

Trudy Odesskogo Politehničeskogo Universiteta, 2017
According to the Strategic Energy Technologies plan, two priorities have been accepted by the European Commis-sion: develop and strengthen energy-efficient systems; increase safety in the use of nuclear energy.
Сергій Миколайович Пелих, М. О. Фролов, А. В. Наливайко, Чжоу Хуійю   +3 more
doaj   +7 more sources