Results 191 to 200 of about 705,564 (243)
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VVER 1000 Khmelnitskiy benchmark analysis calculated by Serpent2
Annals of Nuclear Energy, 2017Abstract 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 +3 more
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Prolonged Operation of Hydro-Accumulators in VVER-1000/V446 Considering Flow Restriction Components
Nuclear TechnologyHydro-accumulators, as a passive part of the emergency core cooling system, have been upgraded in different types of VVER-1000s. The number and performance of these systems are modified in newer types of VVER-1000s to operate at different pressures and ...
S. Hosseini +4 more
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Diagnostics of VVER-1000 Coolant Temperature Pulsations
Atomic Energy, 2019The 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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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 +8 more
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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 +8 more
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VVER-1000 radial reflector modeling by diffusion nodes
Progress in Nuclear Energy, 2006The 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.
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Grounds of VVER-1000 fuel cladding life control
Annals of Nuclear Energy, 2013Abstract A VVER-1000 fuel element (FE) cladding failure estimation method based on creep energy theory (CET-method) is physically grounded. Using CET-method, the VVER-1000 regime and fuel design parameters that determine cladding failure conditions are found.
S.N. Pelykh +2 more
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Analysis of natural circulation phenomena in VVER-1000
Nuclear Engineering and Design, 2004In 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. +2 more
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Examination of VVER-1000 Reactor Pressure Vessel Head
2006This article presents examination VVER-1000 Reactor Pressure Vessel Head (RPVH). The scope of this examination includes the following: visual examination of RPVH interior as well as inside surface of penetration tube ; ultrasound examination of penetration tube from inner side and examination of J-weld area ; eddy current examination of inside surface ...
Pajnić, Mladen, Novosel, Dino
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Equilibrium thorium fuel loading in VVER-1000 reactor
Proceedings of the 2014 15th International Scientific Conference on Electric Power Engineering (EPE), 2014Thorium can be utilized in Pressurized Water Reactors (PWR) as ThO 2 fuel matrix supported by fissile materials. In this analysis, VVER-1000 reactor was taken as a representative of the PWR reactor group. The thorium fuel matrix was mixed with fissile material in form of pure 233U, enriched uranium (19.7 % enrichment) and Reactor-Grade plutonium ...
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Approaches to Neutronic Calculations to Justify the Lifetime Extension for VVER-1000 Control Rods
Nuclear and Radiation SafetyThe uninterrupted operation of Ukrainian NPPs depends not only on timely delivery of fresh fuel, but also on the supply of a number of other critical core elements. One of these critical elements is control rods, which have their own lifetime and need to
O. Mazurok +4 more
semanticscholar +1 more source