Results 131 to 140 of about 688 (173)

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

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

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

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

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