Results 71 to 80 of about 3,636 (213)
Diagnostics of VVER-1000 core states by reactivity perturbations
Global Nuclear SafetyThe self-sustained nuclear fission chain reaction is based on the probabilistic nature of fundamental physical processes. The measure of the dynamics of these processes (state identifier) is taken to be reactivity as a special physical property of the medium or technical system.
V. Y. Shpitser, V. V. Krivin
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Analysis of the residual strength of the high-capacity centrifugal pump with taking into account the effect of corrosive wear due to long-term exploitation [PDF]
, 2019 У даній статті була проведено дослідження для визначення залишкової міцності відцентрового насосу, що працює в понад проектний термін експлуатації в лінії насосів енергоблока АЕС.
Ларін, Олексій Олександрович +2 more
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Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly
Science and Technology of Nuclear Installations, 2019 Thermal reactors have been considered as interim solution for transmutation of minor actinides recycled from spent nuclear fuel. Various studies have been performed in recent decades to realize this possibility.
Vinh Thanh Tran +4 more
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Nuclear Materials and EnergyThe operating conditions are analyzed, mechanical characteristics are calculated pertaining to the 4-year cycle fuel rods of VVER-1000. The fuel rod strength characteristics are considered as applied to steady-state and transient conditions of reactor ...
Stepan Lys, Alexandr Kanyuka
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PARCS/TRACE COUPLING METHODOLOGY FOR ROD EJECTION ON VVER 1000 REACTOR
Acta Polytechnica CTU Proceedings, 2016 The rod ejection (RE) is a design basis accident in accordance with NUREG-0800 and usually studied using point kinetics. In this paper a methodology and a 3D kinetic model is prepared (PARCS), coupled with a thermal hydraulic system code (TRACE) for ...
Marek Ruščák, Guido Mazzini
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Ядерна фізика та енергетика, 2016 Considering the fuel assembly (FA) load history and the nonuniformity of energy release for the fuel elements (FEs) contained in this FA, a method for forecasting of probability of VVER-1000 FE cladding failure due to FE cladding deformation damage ...
S. N. Pelykh +2 more
doaj
EPJ Web of Conferences, 2016 Paper describes the new approach of fitting axial fuel burn-up patterns in peripheral fuel assemblies of VVER-1000 type reactors, on the base of ex-core neutron leakage measurements, neutron-physical calculations and in-core SPND measured data.
Borodkin Pavel +2 more
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Alexandria Engineering Journal, 2018 Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-
Z. Tabadar +3 more
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Применение технологии искрового плазменого спекания для консолидации тугоплавких оксидов и нитридов [PDF]
, 2015 The results of investigation of physical and mechanical properties of ceramic materials manufactured by compaction of alumina, zirconia, and aluminum oxynitride powders using spark plasma sintering (SPS) are presented.
Матренин, Сергей Вениаминович +2 more
core
Nuclear Energy Complexes: Prospects for Development and Cooperation [PDF]
1. 2005–2006 was a critical period in the development of the nuclear complexes of Russian Federation and the Republic of Kazakhstan. These years have ushered in a “nuclear renaissance”.
Vinokurov, Evgeny
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