Results 121 to 130 of about 399 (171)

"Full-Core" VVER-1000 calculation benchmark

Kerntechnik, 2020
Abstract This work deals with the \Full-Core" VVER-1000 calculation benchmark which was proposed on the 26th Symposium of AER [1]. Recently, the calculation benchmarks \Full-Core" VVER-440 [2] and its extension [3] have been introduced in the AER community with positive response [4, 5].
Sprinzl, D., Krysl, V., Mikolas, P., Zavorka, J., Timr, J., Bilodid, Y., Temesvari, E., Pos, I., Kalinin, Y., Shcherenko, A., Aleshin, S., Bahadir, T.   +11 more
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Modernization of Existing VVER-1000 Surveillance Programs

Journal of ASTM International, 2012
Abstract According to generally accepted world practice, evaluation of the reactor pressure vessel (RPV) material behavior during operation is carried out using tests of surveillance specimens. The main objective of the surveillance program consists in insurance of safe RPV operation during the design lifetime and lifetime-extension ...
V. Kochkin, D. Erak, D. Makhotin
openaire   +1 more source

Extended analysis of VVER-1000 surveillance data

International Journal of Pressure Vessels and Piping, 2002
Abstract Up to now 20 surveillance specimen sets of 14 VVER-1000 Reactor Pressure Vessel (RPV) have been evaluated in Russia, Ukraine and Bulgaria by different testing organisations: • Kurchatov Institute, Russia (10 RPVs); • Institute for Nuclear Research, Ukraine (two RPVs); • Institute of Metal Science, Bulgaria (two RPVs).
A Kryukov, D Erak, L Debarberis, F Sevini, B Acosta   +4 more
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Enhanced VVER-1000 Fuel Technology and Performance

Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 2009
The United States Department of Energy, through the Pacific Northwest National Laboratory (PNNL), provides management and technical support for the International Nuclear Safety Program (INSP) to improve the safety level of VVER-1000 nuclear power plants in Central and Eastern Europe.
H. Shah, R. Latorre, G. Raspopin, J. Sparrow   +3 more
openaire   +1 more source

Calculation of “full core” VVER-1000 benchmark

Kerntechnik, 2018
Abstract The 2-D benchmark related to the “full-core” of VVER-1000 was proposed at the AER working group A&B meeting in 2015. Such type of benchmarks requires the adequate specification of the volume surrounding the core where geometry is complex enough.
S. S. Aleshin, A. S. Bikeev, D. S. Oleynik, A. I. Shcherenko   +3 more
openaire   +1 more source

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

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

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
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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
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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