Results 51 to 60 of about 302 (158)

Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants

Energy Science &Engineering, Volume 12, Issue 11, Page 4894-4903, November 2024.
Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants. Abstract This study investigates the impact of hybrid nanoparticles on the temperature of nuclear reactor coolant, with a focus on graphene nanoplatelet (GNP)‐based hybrid nanoparticles. Sixteen different hybrid nanofluids were analyzed, and their
Sinem Uzun, Yasin Genç, Adem Acır
wiley   +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

Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site

Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.
The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
wiley   +1 more source

Multiphysics simulation of fast transients with the FINIX fuel behaviour module

EPJ Nuclear Sciences & Technologies, 2016
FINIX is a recently developed fuel behaviour module that is designed to provide “simple but sufficient” descriptions of the most essential fuel behaviour phenomena in multiphysics simulations.
Ikonen Timo, Syrjälahti Elina, Valtavirta Ville, Loukusa Henri, Leppänen Jaakko, Tulkki Ville   +5 more
doaj   +1 more source

A study into the modes of the VVER-1000 RCP starting in an earlier inoperative loop [PDF]

Nuclear Energy and Technology, 2019
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supporting coupled numerical modeling of neutronic and thermal-hydraulic transients in a VVER reactor plant in operating and emergency conditions, was chosen as ...
Iliya Ye. Bragin, Vladimir I. Belozerov
doaj   +3 more sources

Effect of Modernization of the Third Generation Nuclear Reactors (Model V-446) on Nuclear Safety [PDF]

مجله علوم و فنون هسته‌ای, 2013
A set of Nuclear Reactor model V-446 applied in design AES-91/99 is regarded as an optimized project of reactor VVER-1000 on the basis of reactor model V-320. Improving the neutron- physics characteristics of the active core along with the reconstruction
A Janipour, K Rahimzadeh
doaj  

VVER-1000 reactor vessel metal state monitoring in Ukraine

Nuclear Physics and Atomic Energy, 2011
On the basis of the "hot" cells of the Institute for Nuclear Research of National Academy of Sciences of Ukraine reconstitution technique of VVER reactor vessel metal surveillance specimens, and the main provisions of the reactor vessel radiation loading monitoring procedures and surveillance specimen dosimetry are described in the paper.
V. M. Bukanov, I. M. Vyshnevskyi, M. I. Vlasenko, P. G. Lytovchenko, L. I. Chyrko   +4 more
openaire   +2 more sources

Accident Management in VVER-1000

Science and Technology of Nuclear Installations, 2008
The present paper deals with the investigation study on accident management in VVER-1000 reactor type conducted in the framework of a European Commission funded project. The mentioned study involved both experimental and computational fields. The purpose
F. D'Auria, A. Suslov, N. Muellner, G. Petrangeli, M. Cherubini   +4 more
doaj   +1 more source

CFD Analysis of Thermo-hydraulic Behaviour in the VVER-1000 Reactor Using COMSOL Multiphysics [PDF]

EPJ Web of Conferences
This article presents a two-dimensional Computational Fluid Dynamic (CFD) of the thermohydraulic behaviour of VVER -1000 reactor vessel based on COMSOL Multiphysics.
Rashidov Karim, Bobomurodova Guzal, Abdukhamidov Diydor, Razzokova Moxinur, Mustafoyev Utkir, Monasipova Renata, Ikramov Amirbek   +6 more
doaj   +1 more source

Modelling of the friction-vibration interactions in reactor core barrel couplings

Applied and Computational Mechanics, 2018
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nuclear VVER-type reactor show assembly side clearances.
Zeman V., Hlaváč Z.
doaj   +1 more source