Results 41 to 50 of about 278 (148)
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 Thermal‐hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers, vendors, and research organizations. The computer code user represents a source of uncertainty that can influence the results of system code calculations.
Alessandro Petruzzi +5 more
wiley +1 more source
Computer Assisted Methods in Engineering and Science, 2023 The paper presents selected results of the analysis of thermal and mass flow transient processes within the containments of the WWER-440 and the WWER-1000 nuclear reactors during Loss-of-Coolant Accidents based on the mathematical model and computer ...
Janusz Skorek, Jan Składzień
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An automated boron management system for WWER-1000 nuclear reactors
Trudy Odesskogo Politehničeskogo Universiteta, 2015 The article is devoted to the problem of creating a system of automated control with boron regulation for reactor WWER-1000 series. Using the boron regulation to control WWER-1000 allows to extend its maximum output operation period, ensuring the ...
Taisiya O. Tsiselskaya, Andriy V. Kovtun
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WWER-1000 core loading characteristic influence on irradiation conditions of surveillance specimens and reactor pressure vessel [PDF]
Ядерна фізика та енергетика, 2009 Irradiation conditions of WWER-1000 surveillance specimens and reactor pressure vessel are comparative analyzed for various core loadings. It is proved that the fluences onto specimens don't correlate with ones onto pressure vessel.
V. N. Bukanov +4 more
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Ядерна фізика та енергетика, 2019 Results of the validation of the code package MCPV that is used for the irradiation conditions determination methodology of the pressure vessels and surveillance specimens of the WWER-440 type reactors of Ukrainian NPPs were presented.
S. M. Pugach +3 more
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Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика, 2021 Localizing safety systems are provided to contain radioactive substances in an accident and attenuate ionizing radiation at a modern nuclear power plant.
V. V. Sorokin
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Глобальная 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
An automated boron management system for WWER-1000 nuclear reactors
Trudy Odesskogo Politehničeskogo Universiteta, 2014 The article is devoted to the problem of creating a system of automated control with boron regulation for reactor WWER-1000 series. Using the boron regulation to control WWER-1000 allows to extend its maximum output operation period, ensuring the ...
Таїсія Олександрівна Цисельська +1 more
doaj +4 more sources
Simulation modeling of processes in the WWER-1000 reactor with power control by absorbing rods
Вісник Національного технічного університету "ХПÌ": Системний аналіз, управління та інформаційні технології, 2017 Mathematical models of WWER-1000 nuclear reactor of V-320 series are presented in the form of systems of differential equations in relative state variables.
Валерий Петрович Северин +2 more
doaj +1 more source
ارتقای سطح ایمنی هسته‌ای در نیروگاههای پیشرفته روسیه (WWER) با رآکتور مدل V-392 [PDF]
مجله علوم و فنون هسته‌ای, 2003 پس از سالها بهره‌برداری از نیروگاههای WWER 1000/320 روسی و آشکار شدن نقصهای رآکتور مدل V-320 بکار رفته در آنها، متخصّصان روسی به کمک کارشناسان آمریکایی و آژانس بین‌المللی انرژی اتمی و همچنین مراکز تحقیقاتی داخل و خارج، نیروگاه جدیدی از نوع WWER-1000 با ...
سیدعبدالامیر طبیبیان
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