Results 131 to 140 of about 648 (179)

Comparison of Attenuation Coefficients for VVER-440 and VVER-1000 Pressure Vessels

Journal of ASTM International, 2012
Abstract The paper summarizes the attenuation coefficient of the neutron fluence with E > 0.5 MeV through a reactor pressure vessel for vodo-vodyanoi energetichesky reactor (VVER) reactor types measured and/or calculated for mock-up experiments, as well as for operated nuclear power plant (NPP) units.
Milan Marek, Jan Rataj, Stanislav Vandlik   +2 more
openaire   +1 more source

The SCORPIO-VVER Core Monitoring and Surveillance System for VVER Type of Reactors

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, 2014
The SCORPIO-VVER core monitoring and surveillance system has proved since the first installation at Dukovany NPP in 1999 to be a valuable tool for the reactor operators and reactor physicists. It is now installed on four units of Dukovany NPP (EDU, Czech Republic), on two units of Bohunice NPP (EBO, Slovak Republic) replacing the original Russian VK3 ...
Jozef Molnar, Radim Vocka
openaire   +1 more source

PRESSURE VESSEL CALCULATIONS FOR VVER-440 REACTORS

Reactor Dosimetry in the 21st Century, 2003
For the determination of the fast neutron load of the reactor pressure vessel a mixed calculational procedure was developed. The procedure was applied to the Unit II of Paks NPP, Hungary. The neutron source on the outer surfaces of the reactor was determined by a core design code, and the neutron transport calculations outside the core were performed ...
G, Hordósy, Gy, Hegyi, A, Keresztúri, Cs, Maráczy, E, Temesvári, P, Vértes, E, Zsolnay   +6 more
openaire   +2 more sources

Ballooning Experiments with VVER Cladding

Nuclear Technology, 2005
The results of single-rod and bundle ballooning tests with VVER (E110 type) cladding are presented. The comparative study of E110 and Zircaloy-4 showed a significant difference in behavior at 800 to 1000 deg. C. The local maximum of mechanical strength was observed at a low oxidation rate. The pressurization rate played a considerable role in the burst
Zoltán Hózer, Csaba Gyuőri, Márta Horváth, Imre Nagy, László Maróti, Lajos Matus, Péter Windberg, József Frecska   +7 more
openaire   +1 more source

High-enrichment fuel in VVER

Atomic Energy, 2010
The results of a search for the optimal water-uranium ratio for VVER with no changes to the fuel elements and assemblies are presented. It is shown that decreasing the volume of a fuel pellet while maintaining the same 235 U load as a result of increasing the enrichment will decrease the specific consumption of uranium and increase the run time.
V. F. Tsibulskii, V. D. Davidenko, V. A. Lobyntsev, N. N. Ponomarev-Stepnoi, A. A. Proshkin, E. V. Rodionova, S. V. Tsibulskii   +6 more
openaire   +1 more source

Increasing fuel burnup in VVER

Atomic Energy, 2008
The results of investigations of fuel burnup increase in VVER are presented. The influence of the costs of different technological stages, changes in the number of refuelings and run time, fuel enrichment and waste, and the consumption of natural uranium on increasing burnup is examined. An analysis taking account of the uncertainty of future prices is
E. A. Andrianova, V. F. Tsibul’skii
openaire   +1 more source

Development of an in-reactor monitoring system for VVER

Atomic Energy, 2009
More than 20 power-generating units with VVER-1000 and more than 30 with VVER-440 reactors are currently operating in our country and abroad. This article examines the creation and development of in-reactor monitoring systems for different types of VVER reactors as experience in operating them is gained and the level of knowledge increases.
Yu M Semchenkov, Semchenkov Yu M
exaly   +2 more sources

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