Results 161 to 170 of about 4,383 (200)

Radiation heating of VVER-4440 thermocouple

Kerntechnik, 2020
Abstract Thermocouple located near the coolant outlet of the fuel assembly head may indicate a temperature biased by radiation heating and subsequently affect accuracy of incore measurements. The analysis splits into two parts; coupled neutronphoton Monte Carlo transport to determine radiation heating that serves as the input to heat ...
Lovecký, Martin, Šik, Jan
openaire   +3 more sources

Component vibration of VVER-reactors — diagnostics and modelling

Progress in Nuclear Energy, 1995
Abstract Flow induced vibrations of reactor pressure vessel (RPV) internals (control element and core barrel motions) at VVER-440 reactors have lead to the development of dedicated methods for on-line monitoring. These methods need a certain developed stage of the faults to be detected. To achieve a real sensitive early detection of mechanical faults
Altstadt, E., Liewers, P., Scheffler, M., Schumann, P., Weiß, F.-P.   +4 more
openaire   +2 more sources

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

Simulation of a Transient Process in VVER-1200 by Means of the Athlet/BIPR-VVER Coupled Neutronics and Thermohydraulic Code

Atomic Energy, 2020
The results of a simulation, performed using the code ATHLET/BIPR-VVER (Russia, Germany), of tests on connecting a single main circulation pump (MCP) unit with three operating units during operation of VVER-1200 at 26% normal power level are presented.
A. V. Baikov, A. A. Dubov, A. V. Kotsarev, B. E. Shumskii   +3 more
openaire   +1 more source

VVER-440 and VVER-1000 Reactor Dosimetry Benchmark—BUGLE-96 Versus ALPAN VII.0

Journal of ASTM International, 2012
Analytical results of the vodo-vodyanoi energetichesky reactor-(VVER-) 440 and VVER-1000 reactor dosimetry benchmarks developed from engineering mockups at the Nuclear Research Institute Rez LR-0 reactor are discussed. These benchmarks provide accurate determination of radiation field parameters in the vicinity and over the thickness of the reactor ...
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

Comparison of microstructural features of radiation embrittlement of VVER-440 and VVER-1000 reactor pressure vessel steels

Journal of Nuclear Materials, 2002
Comparative microstructural studies of both surveillance specimens and reactor pressure vessel (RPV) materials of VVER-440 and VVER-1000 light water reactor systems have been carried out, following irradiation to different fast neutron fluences and of the heat treatment for extended periods at the operating temperatures.
E.A. Kuleshova, B.A. Gurovich, Ya.I. Shtrombakh, D.Yu. Erak, O.V. Lavrenchuk   +4 more
openaire   +1 more source

Monitoring of the VVER nuclear reactor internals

Nuclear Engineering and Design, 1997
Abstract This paper presents a review of the published pressurized water reactor accidents caused by internal vibrations. These accidents are evaluated with respect to their impact on the safety and economy of nuclear power generation. Subsequently, criteria for a monitoring system which would allow the prevention of such accidents are proposed ...
openaire   +1 more source

Safety of VVER-440 Reactors

2011
Safety of VVER-440 Reactors , Safety of VVER-440 Reactors , کتابخانه الکترونیک و دیجیتال ...
openaire   +1 more source