Results 11 to 20 of about 259 (131)

Digital acoustic model of an NPP pressurizer with WWER

Global Nuclear Safety, 2023
It is experimentally proven that the main cause of vibration excitation of equipment and internals of the main circulation circuit (MCC) are acoustic standing waves (ASW) and main circulation pumps (MCP). Usage of an interdisciplinary approach made it possible to create a digital acoustic model of pressurizer system with pipelines attached to it and ...
K. N. Proskuryakov, M. S. Khvostova, R. M. Ismail, K. A. Yakovlev   +3 more
openaire   +2 more sources

Estimation of local linear heat rate jump values in the variable loading mode [PDF]

Ядерна фізика та енергетика, 2011
A method of the WWER-1000 fuel element cladding durability analysis using the energy creep theory makes it possible to determinate the WWER-1000 reactor permissible operation time for the mode of varying loading. But the WWER-1000 axial segments and fuel
S. N. Pelykh, R. L. Gontar, T. V. Tsiselskaya   +2 more
doaj  

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

Глобальная 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, V. I. Savander, G. V. Tikhomirov   +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, Володимир Миколайович Ревка, Людмила Іванівна Чирко, Олександр Вікторович Тригубенко, Юрій Віталійович Чайковський   +4 more
doaj   +5 more sources

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

ACOUSTIC MODELING AND PREVENTION OF VIBROACOUSTIC RESONANCES IN THE PRIMARY CIRCUIT OF NUCLEAR POWER PLANTS WITH WWER-1200 REACTORS

Надежность и качество сложных систем
Background. The commissioning of new nuclear power plants with WWER-1200 water-water energetic reactors, including the Akkuyu Nuclear Power Plant, requires a high level of operational safety and seismic resistance.
Konstantin N. Proskuryakov, Ragy M. N. H. Ismail, Marina S. Khvostova   +2 more
doaj   +1 more source

Development of a criterion for assessment of fuel washout during operation of WWER power units [PDF]

Nuclear Energy and Technology, 2020
Fuel failures may occur during operation of nuclear power plants. One of the possible and most severe consequences of a fuel failure is that fuel may be washed out from the leaking fuel rod into the coolant.
Igor A. Evdokimov, Andrey G. Khromov, Petr M. Kalinichev, Vladimir V. Likhanskii, Aleksey A. Kovalishin, Mikhail N. Laletin   +5 more
doaj   +3 more sources

Determination of irradiation conditions of WWER-1000 reactor internals [PDF]

Ядерна фізика та енергетика, 2006
The calculational procedure for determination of irradiation conditions of WWER-1000 reactor internals is presented. Using developed procedure, irradiation conditions of WWER-1000 reactor internals, first of all, baffle and barrel, are determined for a
S. M. Pugach, V. N. Bukanov, O. V. Grytsenko, V. L. Dyemokhin   +3 more
doaj  

Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000

Ядерна фізика та енергетика, 2019
The research presents an analysis of the known results in modeling the maximum design accident (MDA) using the code RELAP5/V3.2 with Westinghouse fuel assemblies’ (WFA) diversification in WWER-1000 reactors.
V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi   +4 more
doaj   +1 more source

Reply to V. I. Borysenko's comment on the article: "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" [PDF]

Ядерна фізика та енергетика, 2020
: Reply to V. I. Borysenko's 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" https://doi.org/10.15407 ...
V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, V. Yu. Gryb, V. M. Vashchenko   +4 more
doaj   +1 more source