Results 1 to 10 of about 15 (15)

НЕОПРЕДЕЛЕННОСТЬ В РАСЧЕТАХ ИЗ-ЗА «МГНОВЕННЫХ» АВАРИЙНЫХ СИТУАЦИЙ НА ВВЭР-1000

open access: yesГлобальная ядерная безопасность, 2022
The paper shows the occurrence of pressure waves and their propagation in the equipment of the first circuit of the WWER-1000 reactor plant in emergency situations associated with an instantaneous stop of the Main circulation pump or a two-way flow with ...
S. P. Nikonov, D. A. Amer
doaj   +1 more source

Forecasting the Operation of Sealing Joints of Transport Locks of WWER-1000 and WWER-1200 Power Units in Operational Modes

open access: yesГлобальная 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

Influence of Fuel Temperature Distribution Dependence on Neutron-Physical Characteristics of Nuclear Core with WWER-1000 (1200)

open access: yesГлобальная ядерная безопасность, 2022
This paper presents the results of the influence of reactivity on fuel temperature distribution for the neutron-physical characteristics of WWER 1000-1200 cores, which in turn affects the parameters of Xenon oscillation.
R. T. Al Malkawi, L. J. Zadan
doaj   +1 more source

Analysis and optimization of energy release and fuel burnup nonuniformity in the WWER-1000 fuel assembly

open access: yesГлобальная ядерная безопасность, 2023
The paper considers and systematises the options of fuel assemblies (FAs) for the WWER-1000 reactor. In the Serpent neutron-physics code, an infinite-height fuel assembly with six fuel pins is modelled using the U49G6 pattern used in the WWER-1000 «large
A. A. Lapkis   +3 more
doaj   +1 more source

Investigation of Absorber Concentration Changes During Maneuvering Operation in VVER 1000 Reactor

open access: yesГлобальная ядерная безопасность, 2022
Boron carbide, Dysprosium, Silver, etc have a lot of unique properties, high neutron absorption, chemical stability, high melting temperature, low density, and low price. These elements are widely using in the VVER power reactors.
R. S. Anisur, M. A. Uvakin
doaj   +1 more source

Comparative Study of Spectral Regulation Range of Excess Reactivity Control in Pressurized Water Reactors Using Zirconium Displacers for Uranium and Thorium Fuel Cycles

open access: yesГлобальная ядерная безопасность, 2022
The compensation for the excess reactivity in the pressurized water reactors WWER is realized with high neutron absorber materials. The traditional excess reactivity regulation methods lead to unfeasible neutron utilization and reduce the breeding ...
A. I. Elazaka   +2 more
doaj   +1 more source

Potential and possibility of extending the campaign to increase VVER-1000 power units on sliding distribution of the secondary circuit

open access: yesГлобальная ядерная безопасность, 2023
The paper considers the efficiency and possibility of implementing into the operational practice of VVER-1000 power units the campaign extension mode at the sliding pressure of the second circuit.
A. S. Grachev   +2 more
doaj   +1 more source

Selecting Burnup Algorithms in OpenMC Using the Calculated Benchmark of LEU Assembly and MOX Fuel

open access: yesГлобальная ядерная безопасность, 2023
OpenMC is a state-of-the-art Monte Carlo neutron transport simulation code that uses the Python programming language as an API. OpenMC supports eight burnout simulation algorithms.
Hamza A Tanash   +5 more
doaj   +1 more source

АВТОМАТИЗИРОВАННОЕ УПРАВЛЕНИЕ ПРОЦЕССОМ БОРНОГО РЕГУЛИРОВАНИЯ В ЯДЕРНЫХ РЕАКТОРАХ ТИПА ВВЭР-1000

open access: yesАвтоматизация технологических и бизнес-процессов, 2015
Рассмотрена актуальная задача создания системы автоматизированного управления процессом борного регулирования в реакторах типа ВВЭР-1000. Результаты решения этой задачи были использованы длядальнейшей разработки компьютерно-интегрированной системы ...
Т. А. Цисельская   +1 more
doaj   +1 more source

АКСИАЛЬНЫЙ ОФСЕТ КАК МЕРА УСТОЙЧИВОСТИ ЛЕГКОВОДНОГО ЯДЕРНОГО РЕАКТОРА ПРИ СУТОЧНОМ МАНЕВРЕ МОЩНОСТЬЮ.

open access: yesАвтоматизация технологических и бизнес-процессов, 2015
Требованиями, предъявляемыми при эксплуатации энергоблока в маневренном режиме, являются высокая надежность и безопасность энергоблока, которые зависят от устойчивости реактора при переходе с одного уровня мощности на другой.
М. В. Никольский
doaj   +1 more source

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