Results 91 to 100 of about 4,383 (200)

CFD Analysis of Downcomer of Nuclear Reactor VVER 440

, 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.
Gálik Gálik, Jakubec Jakub, Paulech Juraj, Sedlár Tibor, Kutiš Vladimír   +4 more
core   +1 more source

Localizing Perturbations in Pressurized Water Reactors Using One-Dimensional Deep Convolutional Neural Networks. [PDF]

Sensors (Basel), 2021
Pantera L, Stulík P, Vidal-Ferràndiz A, Carreño A, Ginestar D, Ioannou G, Tasakos T, Alexandridis G, Stafylopatis A.   +8 more
europepmc   +1 more source

Structural and Parametric Optimization of S-CO₂ Nuclear Power Plants. [PDF]

Entropy (Basel), 2021
Rogalev N, Rogalev A, Kindra V, Komarov I, Zlyvko O.   +4 more
europepmc   +1 more source

In-air and in-water performance comparison of Passive Gamma Emission Tomography with activated Co-60 rods. [PDF]

Sci Rep, 2023
Virta R, Bubba TA, Moring M, Siltanen S, Honkamaa T, Dendooven P.   +5 more
europepmc   +1 more source

Vliv proudeni v sestupne sachte reaktoru VVER-440 a VVER-1000 na teplotni a rychlostni pole na vstupu do AZ.

, 2003
The objective of this work is the influence of flow in downcomer to the temperature and velocity field at the core inlet of reactors VVER-440 and VVER-1000 using computer code FLUENT 6.1.
Hartel, P. (and others), Zacha, P., Prosicky, M., Ceske vysoke uceni technicke v Praze, Praha (Czech Republic)   +3 more
core  

Results of Researches in the Frame Work of the Project “OECD PSB-VVER”

, 2010
Under OECD PSB-VVER project, five experiments were performed in the PSB-VVER test facility. They are: 11% upper plenum break, natural circulation test, small break in cold leg, leak from primary circuit into secondary one and large break in cold leg. The
Ilya V. Elkin, Sergey S. Pylev, Vladimir I. Melikhov, Oleg I. Melikhov, Sergey M. Nikonov   +4 more
core   +1 more source

Study of Transient States in VVER Pressurized Water Reactors

, 2017
Práce se zabývá přechodovými procesy pro tlakovodní reaktory typu VVER a na základě sestavených modelových úloh demonstruje rozdíly mezi chováním aktivní zóny při vybraných přechodových procesech u reaktorů VVER-440 a VVER-1000.
Jantač František
core  

Comparative Analysis of Emergency Planning Zone and Control Room Habitability for Potential Nuclear Reactor Deployment in Ghana. [PDF]

Int J Environ Res Public Health, 2022
Christina P, Kim J.
europepmc   +1 more source

Analysis of VVER-1200 thermal characteristics using analytical calculation validated by PCTran simulator

Discover Mechanical Engineering
An analytical method was developed to predict the thermal parameters of the VVER-1200 pressurized water reactor (PWR). The peak temperatures of the fuel, outer fuel surface temperature, inner cladding surface temperature, outer cladding surface ...
Alexander G. Korotkikh, Christopher Joseph Odii   +1 more
doaj   +1 more source

Benchmarking of COBAYA3 pin-by-pin for VVER

, 2012
This paper presents results of the benchmarking of COBAYA3 pin-by-pin for VVER-1000 obtained in the frame of the EU NURISP project. The 3D lattice solver in COBAYA3 uses transport corrected multi-group diffusion approximation with side-dependent interface discontinuity factors of GET or Selengut Black Box type.
Zheleva, Nonka, Herrero Carrascosa, José Javier, Todorova, Galina, Ivanov, Plamen, Kolev, Nikola   +4 more
openaire   +2 more sources