Results 171 to 180 of about 3,636 (213)

Neutronic study of nanofluids application to VVER-1000

Annals of Nuclear Energy, 2010
Abstract The change in neutronic parameters of the VVER-1000 nuclear reactor core attributable to the use of nanoparticle/water (nanofluid) as coolant is presented in this paper. Optimization of type and volume fraction of nanoparticles in water that affect the safety enhancement of core primary parameters is intended in this study. Reactivity change,
K. Hadad, A. Hajizadeh, K. Jafarpour, B.D. Ganapol   +3 more
openaire   +1 more source

Analysis of natural circulation phenomena in VVER-1000

Nuclear Engineering and Design, 2004
In all light water reactors (LWR), natural circulation is an important passive heat removal mechanism. In the present paper, the natural circulation phenomena are studied with reference to step-wise coolant inventory reduction and a small break loss-of-coolant-accident (SBLOCA) in the cold leg of VVER-1000.
MOUSAVIAN S. K., D'AURIA, FRANCESCO SAVERIO, SALEHI M. A.   +2 more
openaire   +2 more sources

Characterization of gamma flux in VVER-1000 internals

Journal of Nuclear Engineering and Radiation Science
Abstract Accurate prediction of gamma flux in reactor internals is essential for structural assessments studies. This paper presents gamma spectrum measurements in a VVER-1000 full-scale mock-up at the LR-0 reactor, using a stilbene scintillator connected to the NGA-01 spectrometer.
Tomáš Czakoj, Michal Košťál, Zdeněk Matěj   +2 more
openaire   +1 more source

VVER-1000 SFAT

2002
IAEA needed a rugged spent fuel attribute tester, SFAT, for verifying spent fuel assemblies of the Ukrainian VVER-1000 reactors in line with IAEA safeguards measurement standards and criteria of verification. Spent fuel verification using the existing Improved Cerenkov Viewing Device is becoming more and more difficult and sometimes impossible ...
Tiitta, Antero, Tarvainen, Matti, Iievlev, Serhii, Dvoeglazov, Alexander, Bytchkov, Valerij, Popescu, Dorel, Lee, Young-Gil, Hosoya, Michio, Goulo, Valery   +8 more
openaire   +1 more source

Automatic Modeling of VVER-1000 Power Maneuvers

Atomic Energy, 2018
A special version of the IR code is described. The purpose of this code is to generate recommendations for the reactor operator when operating in a maneuvering regime, automate boron regulation, and study the maneuvering characteristics of VVER-1000 fuel loads.
openaire   +1 more source

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, Natalya A. Shulgan, Yaroslav I. Shtrombakh, Tatyana I. Titova, Yury A. Nikolaev, Marina G. Blinova   +5 more
openaire   +1 more source

VVER-1000 radial reflector modeling by diffusion nodes

Progress in Nuclear Energy, 2006
The two commonly used approaches to describe the VVER radial reflectors in diffusion codes, by core-reflector albedos and by a ring of diffusion assembly size nodes, are discussed. The advantages and disadvantages of the first approach are presented first, then the Koebke's equivalence theory is outlined and its implementation for the VVER radial ...
Petkov, P. T., Mittag, S.
openaire   +2 more sources

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, Ondrej Chvala, Nicholas P. Luciano, G. Ivan Maldonado   +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 ...
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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