Results 61 to 70 of about 648 (179)

Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

EPJ Web of Conferences, 2016
Usually the synthesis of two-dimensional and one-dimensional discrete ordinate calculations is used to evaluate neutron fluence on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation embrittlement.
Dzhalandinov A., Tsofin V., Kochkin V., Panferov P., Timofeev A., Reshetnikov A., Makhotin D., Erak D., Voloschenko A.   +8 more
doaj   +1 more source

Modernization of Cross Section Library for VVER-1000 Type Reactors Internals and Pressure Vessel Dosimetry

EPJ Web of Conferences, 2016
The broad-group library BGL1000_B7 for neutron and gamma transport calculations in VVER-1000 internals, RPV and shielding was carried out on a base of fine-group library v7-200n47g from SCALE-6 system.
Voloschenko Andrey, Zaritskiy Sergey, Egorov Aleksander, Boyarinov Viktor   +3 more
doaj   +1 more source

Experimental studies into the fluid dynamic performance of the coolant flow in the mixed core of the Temelin NPP VVER-1000 reactor

Nuclear Energy and Technology, 2015
The paper presents the results of studies into the interassembly coolant interaction in the Temelin nuclear power plant (NPP) VVER-1000 reactor core.
S.M. Dmitriev, D.V. Doronkov, Ye.N. Polozkova, A.N. Pronin, V.D. Sorokin, A.Ye. Khrobostov   +5 more
doaj   +1 more source

Estimation of material degradation of VVER-1000 baffle

EPJ Web of Conferences, 2017
The planned lifetime of the first commercial VVER-1000 units were designed for 30 to 35 years. Most of the early VVER plants are now reaching and/or passing the 35-year mark.
Harutyunyan Davit, Košál Michal, Vandlík Stanislav, Hojná Anna, Schulc Martin, Flibor Stanislav   +5 more
doaj   +1 more source

An analysis of the “Fast” noise measurements of the dynamic VVER processes [PDF]

Nuclear Energy and Technology
Studies of maneuverable modes of VVER to confirm the possibility of participation of nuclear power plants in the mode of daily carrying capacity have been conducted for quite a long time. Tests at various nuclear power plants with VVER-1000 (Zaporizhzhia
Gennady V. Arkadov, Vladimir I. Pavelko, Mikhail T. Slepov   +2 more
doaj   +3 more sources

Vanquishing the computational cost of passive gamma emission tomography simulations leveraging physics-aware reduced order modeling. [PDF]

Sci Rep, 2023
Cavallini N, Ferretti R, Bostrom G, Croft S, Fassi A, Mercurio G, Nonneman S, Favalli A.   +7 more
europepmc   +1 more source

Vertical steam generators for VVER NPPs [PDF]

Nuclear Energy and Technology, 2018
Steam generators for NPPs are the important large-sized metal consuming equipment of nuclear power installations. Efficiency of steam generator operation determines the overall service life of the whole nuclear facility. The main aim of the current study is to analyze advantages and shortcomings of horizontal and vertical types of steam ...
openaire   +4 more sources

Role of passive safety systems in prevention and mitigation of severe accidents at nuclear power plants

Trudy Odesskogo Politehničeskogo Universiteta, 2022
Fukushima Daiichi accidents led to the worldwide update of the NPP safety requirements. Particular attention was paid to severe accidents both during the design of new NPP units and during the safety reassessment of existing ones.
Володимир Петрович Кравченко, Максим Павлович Вишемірський   +1 more
doaj  

Realizing a deep reinforcement learning agent for real-time quantum feedback. [PDF]

Nat Commun, 2023
Reuer K, Landgraf J, Fösel T, O'Sullivan J, Beltrán L, Akin A, Norris GJ, Remm A, Kerschbaum M, Besse JC, Marquardt F, Wallraff A, Eichler C.   +12 more
europepmc   +1 more source

CFD Analysis of Downcomer of Nuclear Reactor VVER 440

Journal of Mechanical Engineering, 2016
The paper is focused on CFD analyses of the coolant flow in the nuclear reactor VVER 440. The goal of the analyses is to investigate the influence of the orifice diameter on the mass flow through individual fuel assemblies in the reactor core.
Kutiš Vladimír, Jakubec Jakub, Paulech Juraj, Gálik Gálik, Sedlár Tibor   +4 more
doaj   +1 more source