Results 81 to 90 of about 10,176 (222)

Pressure vessels pressurized water reactors [PDF]

, 2014
Cílem bakalářské práce je vypracování rešerše na téma tlakové nádoby tlakovodních reaktorů. Dále provést přehled jednotlivých konstrukčních řešeních tlakové nádoby tlakovodního reaktoru.
Horváth, Radovan
core  

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

Nuclear Safety Evaluation in Steam Generators [PDF]

, 2014
Import 05/08/2014Tato bakalářská práce se zabývá hodnocením všech typů parogenerátoru a porovnání jejich základních parametrů s ohledem na jadernou bezpečnost. V prvních kapitolách jsou popsány parametry určitých parogenerátorů. Dále je přiblížen samotný
Vobořil, Martin
core  

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

Project PISA: Phosphorus Influence on Steel Ageing [PDF]

, 2008
The integrity of the pressure vessel is vital to the safe operation of a nuclear reactor. It is therefore necessary to monitor or predict the changes in the reactor pressure vessel (RPV) material during operation.
ACOSTA IBORRA Beatriz, BACON David, BALLESTEROS Antonio, BRUMOVSKY Milan, DONALDSON Andrew, ENGLISH Colin, GILLEMOT Ferenc, HORVATH Marta, KIZLER Peter, KYTKA Milos, LANGER Reinhard, NEONEN Pentti, ORTNER Susan, SAILLET Sebastian, SEVINI Filippo   +14 more
core  

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

World Nuclear Industry Status Report 2013 [PDF]

, 2013
Two years after the Fukushima disaster started unfolding on 11 March 2011, its impact on the global nuclear industry has become increasingly visible. Global electricity generation from nuclear plants dropped by a historic 7 percent in 2012, adding to the
Froggatt, Antony, Schneider, Mycle
core