Results 81 to 90 of about 675,221 (193)

An analysis of the fuel element cladding failure parameter considering the nonuniformity of energy release in a fuel assembly

Ядерна фізика та енергетика, 2016
Considering the fuel assembly (FA) load history and the nonuniformity of energy release for the fuel elements (FEs) contained in this FA, a method for forecasting of probability of VVER-1000 FE cladding failure due to FE cladding deformation damage ...
S. N. Pelykh, M. V. Maksimov, S. D. Ryabchikov   +2 more
doaj  

Methodology of Fuel Burn Up Fitting in VVER-1000 Reactor Core by Using New Ex-Vessel Neutron Dosimetry and In-Core Measurements and its Application for Routine Reactor Pressure Vessel Fluence Calculations

EPJ Web of Conferences, 2016
Paper describes the new approach of fitting axial fuel burn-up patterns in peripheral fuel assemblies of VVER-1000 type reactors, on the base of ex-core neutron leakage measurements, neutron-physical calculations and in-core SPND measured data.
Borodkin Pavel, Borodkin Gennady, Khrennikov Nikolay   +2 more
doaj   +1 more source

PARCS/TRACE COUPLING METHODOLOGY FOR ROD EJECTION ON VVER 1000 REACTOR

Acta Polytechnica CTU Proceedings, 2016
The rod ejection (RE) is a design basis accident in accordance with NUREG-0800 and usually studied using point kinetics. In this paper a methodology and a 3D kinetic model is prepared (PARCS), coupled with a thermal hydraulic system code (TRACE) for ...
Marek Ruščák, Guido Mazzini
doaj   +1 more source

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

Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode

Alexandria Engineering Journal, 2018
Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-
Z. Tabadar, M. Jabbari, M. Khaleghi, M. Hashemi-Tilehnoee   +3 more
doaj   +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

Investigation of Coolant Mixing in Reactor VVER-1000

, 2011
We present an experimental investigation of coolant mixing in downcomer and lower plenum of VVER-1000 here. The arrangement of the problem, the methodology and results are discussed. Three groups of experiments simulating coolant mixing were executed: in conditions of RCP start-up, during natural circulation recovery in the course of SB LOCA and in ...
Lysenkov E. A., Bezrukov Yu. A., Ulianovskiy D. V., Zaytsev D. V., Bykov M. A., Shishov A. V., Moretti Fabio, Del Nevo Alessandro, D’Auria F., Rohde U., Höhne T., Gallori Daniele   +11 more
openaire   +3 more sources

Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility

Science and Technology of Nuclear Installations, 2012
The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000.
A. Del Nevo, M. Adorni, F. D'Auria, O. I. Melikhov, I. V. Elkin, V. I. Schekoldin, M. O. Zakutaev, S. I. Zaitsev, M. Benčík   +8 more
doaj   +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

Influence of Flow Parameters on Critical Heat Flux in VVER-1000 nuclear reactor

, 2023
Tato bakalářská práce pojednává o závislosti vstupních parametrů na rezervě do krize varu v jaderném reaktoru VVER-1000. První část práce se věnuje popisu VVER-1000 a s ním svázané Jaderné Elektrárny Temelín, dále využívanému jadernému palivu a ...
Vojtěch Soukup
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