Results 11 to 20 of about 186 (119)
Глобальная ядерная безопасность, 2022 The relevance of this work is determined by the need to predict the operation of sealing joints of transport locks of WWER-1000 and WWER-1200 power units in operational modes. The results of tests of rubber seals for tightness are given.
S. A. Kuzin +3 more
doaj +1 more source
Analysis of WWER-1000 Fuel Deformation Using the Refueling Machine Control System
Глобальная ядерная безопасность, 2022 The analysis of the geometric dimensions of fuel assemblies, whose change may lead to mashing of the cassettes in the core, is performed at this stage only after removing the fuel assemblies from the reactor.
A. A. Lapkis +2 more
doaj +1 more source
Possibility of a life-time extension for wwer-1000 reactor pressure vessels beyond the design period
Trudy Odesskogo Politehničeskogo Universiteta, 2020 At present a life-time extension for WWER-1000 reactor pressure vessels is an actual issue in Ukraine. For a decision about the life-time extension it is needed to assess mechanical properties and the critical brittleness temperature TK for the RPV ...
Микола Геннадійович Голяк +4 more
doaj +5 more sources
IMPROVING THE EFFICIENCY OF THE UNIT OF THE ZAPORIZHZHIA NPP WITH A WWER-1000 REACTOR
Problems of Atomic Science and Technology, 2020 Improving the efficiency of the unit of the Zaporizhzhia NPP with a WWER-1000 reactor, by reducing the water temperature at the inlet to the condenser. The work describes the description of the NPP and the nuclear power reactor WWER-1000, by reducing the water temperature at the inlet to the condenser.
Cheilytko, A.A. +2 more
openaire +2 more sources
Decision support system for WWER-1000 reactivity management
Journal of Physics: Conference Series, 2020 Abstract The article describes the developed software for automating operational calculations of reactivity changes of the water-water energetic reactor (WWER-1000). The main calculation dependencies, screen forms and test results on the Rostov nuclear power plant (Rostov NPP) are given. The calculation accuracy increase is shown.
M A Kolomiets +2 more
openaire +1 more source
On the Modelling of Thermal Aging through Neutron Irradiation and Annealing
Advances in Materials Science and Engineering, Volume 2018, Issue 1, 2018., 2018 A new method predicting long‐term thermal embrittlement of steel caused by P segregation is verified. The method is based on the results of impact strength or fracture toughness tests using specimens after relatively short‐term neutron irradiation followed by annealing.
Boris Margolin +4 more
wiley +1 more source
A method for limitation of probability of accumulation of fuel elements claddings damage in WWER
Trudy Odesskogo Politehničeskogo Universiteta, 2014 The aim is to reduce the probability of accumulation of fuel elements claddings damage by developing a method to control the properties of the fuel elements on stages of design and operation of WWER.
Сергій Миколайович Пелих +2 more
doaj +7 more sources
Gas‐Cooled Thorium Reactor with Fuel Block of the Unified Design
Advances in Materials Science and Engineering, Volume 2015, Issue 1, 2015., 2015 Scientific researches of new technological platform realization carried out in Russia are based on ideas of nuclear fuel breeding in closed fuel cycle and physical principles of fast neutron reactors. Innovative projects of low‐power reactor systems correspond to the new technological platform.
Igor Shamanin +4 more
wiley +1 more source
A Comprehensive Survey on Particle Swarm Optimization Algorithm and Its Applications
Mathematical Problems in Engineering, Volume 2015, Issue 1, 2015., 2015 Particle swarm optimization (PSO) is a heuristic global optimization method, proposed originally by Kennedy and Eberhart in 1995. It is now one of the most commonly used optimization techniques. This survey presented a comprehensive investigation of PSO.
Yudong Zhang +3 more
wiley +1 more source
Comment on the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi. "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" [PDF]
Ядерна фізика та енергетика, 2020 Comment to the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi. "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000", https://doi.org/10.15407/jnpae2019.02 ...
V. I. Borysenko
doaj +1 more source