Results 131 to 140 of about 399 (171)
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Mechanical Properties Distribution in Welds and Forging of VVER-1000

Volume 6: Materials and Fabrication, Parts A and B, 2009
Study of weld metal and shell metal of VVER-1000 reactor is carried out. Metal of the control welded joint performed to the welds Nos. 3 and 4 and metal of the test ring of supporting shell is used. For each of the analyzed materials the bending tests of Charpy specimens are carried out according to the surveillance specimens testing procedure ...
Anna A. Chernobaeva   +5 more
openaire   +1 more source

VVER 1000 Khmelnitskiy benchmark analysis calculated by Serpent2

Annals of Nuclear Energy, 2017
Abstract This paper presents results obtained by reproducing a VVER-1000 lattice physics benchmark using the Serpent2 code. The benchmark data are related to the initial cycles of the Khmelnitskiy nuclear power plant. This study compares results obtained with the Serpent2 code against those calculations published in the benchmark document.
Ondrej Novak   +3 more
openaire   +1 more source

Diagnostics of VVER-1000 Coolant Temperature Pulsations

Atomic Energy, 2019
The temperature pulsations arising in coolant flow at the entry into FA are examined from the standpoint of the possibility of their diagnostics by thermocouples of the protective-tube block are examined. It is shown that the temperature pulsations remain in the FA and can be recorded at the exit from FA by means of the in-reactor monitoring system ...
openaire   +1 more source

VVER 1000 Pressurizer System and Control Modelling in Dymola

Volume 9: Student Paper Competition, 2018
The pressurizer is responsible for controlling the pressure and temperature in the primary circuit of the nuclear power plant. It is basically a pressure vessel, filled partially with water and partially with steam at saturation state. The controlling process can be described by two regimes, either by the self-control regime or by the automatic control
Anna Fořtová, Filip Ježek
openaire   +1 more source

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   +2 more
openaire   +1 more source

Scaling of Small Break LOCA in VVER 1000 System

2005
This paper deals with the problem of scaling complex scenario measured experimental facilities and replicated by the use of Cathare2 code. ‘Kv-scaled’ calculation an important role in the frame of the “on-transient qualification” of the nodalization owing the procedure envisaged at Pisa University) and to evaluate the importance oe scale-distortions in
CHERUBINI M   +3 more
openaire   +2 more sources

Equilibrium thorium fuel loading in VVER-1000 reactor

Proceedings of the 2014 15th International Scientific Conference on Electric Power Engineering (EPE), 2014
Thorium can be utilized in Pressurized Water Reactors (PWR) as ThO 2 fuel matrix supported by fissile materials. In this analysis, VVER-1000 reactor was taken as a representative of the PWR reactor group. The thorium fuel matrix was mixed with fissile material in form of pure 233U, enriched uranium (19.7 % enrichment) and Reactor-Grade plutonium ...
openaire   +1 more source

VVER-1000 Regulatory Forum Benchmark

Transactions of the American Nuclear Society, 2020
K. Velkov, R. Henry
openaire   +1 more source

CFD Simulation of Slug Mixing in VVER-1000 Reactor

Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 2006
Recently, the safety analyses of VVER and PWR reactors have dealt with the possibility of reactivity-induced accidents related to the penetration of a water slug with low boron concentration into the reactor core. Loop seals at the reactor coolant pump (RCP) suction are the most likely places for the formation of these slugs.
openaire   +1 more source

VVER-1000 SFAT-Specification of an industrial prototype

2000
The project to develop a Spent Fuel Attribute Tester (SFAT) for Ukrainian VVER-1000 facilities is going on under the Task FIN A 1073 of the Finnish Support Programme to the IAEA safeguards. In the SFAT method [1] the verification is based on an unambiguous detection of gamma radiation of the fission products.
Tiitta, Antero   +4 more
openaire   +1 more source

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