Results 1 to 10 of about 10,176 (222)

Accident Management in VVER-1000 [PDF]

open access: yesScience 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   +4 more
doaj   +5 more sources

Evaluating machine learned nuclear data precision in full core nuclear reactor Monte Carlo neutronics and computational efficiency analyses [PDF]

open access: yesScientific Reports
This study evaluates the novel machine learning based reduction of cross-sections and energy grid of continuous-energy nuclear data for one year full core Monte Carlo criticality and burn-up analysis using OpenMC.
Alexander Hashemi   +2 more
doaj   +2 more sources

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

open access: yesScience 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   +8 more
doaj   +4 more sources

Strain Range Dependent Cyclic Hardening of 08Ch18N10T Stainless Steel-Experiments and Simulations. [PDF]

open access: yesMaterials (Basel), 2019
This paper describes and presents an experimental program of low-cycle fatigue tests of austenitic stainless steel 08Ch18N10T at room temperature. The low-cycle tests include uniaxial and torsional tests for various specimen geometries and for a vast ...
Fumfera J   +4 more
europepmc   +3 more sources

Assessment of the TiO2/water nanofluid effects on heat transfer characteristics in VVER-1000 nuclear reactor using CFD modeling

open access: yesNuclear Engineering and Technology, 2015
The most important advantage of nanoparticles is the increased thermal conductivity coefficient and convection heat transfer coefficient so that, as a result of using a 1.5% volume concentration of nanoparticles, the thermal conductivity coefficient ...
GholamReza Ansarifar
exaly   +3 more sources

SERPENT/SUBCHANFLOW COUPLED BURNUP CALCULATIONS FOR VVER FUEL ASSEMBLIES [PDF]

open access: yesEPJ Web of Conferences, 2021
The continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ commercial goals represent a push for the development of highly accurate methodologies in reactor physics.
Ferraro Diego   +6 more
doaj   +1 more source

3-D COUPLED SIMULATION OF A VVER 1000 WITH PARCS/ATHLET [PDF]

open access: yesEPJ Web of Conferences, 2021
A new OECD/NEA benchmark entitled “Reactivity compensation with diluted boron by stepwise insertion of control rod cluster” is starting. This benchmark, based on high quality measurements performed at the NPP Rostov Unit 2, aims to validate and assess ...
Henry Romain   +3 more
doaj   +1 more source

COUPLING OF nTRACER TO COBRA-TF FOR HIGH-FIDELITY ANALYSIS OF VVERs [PDF]

open access: yesEPJ Web of Conferences, 2021
Paul Scherrer Institut is developing a high-resolution multi-physics core solver for VVER analysis. This work presents the preliminary stages of the development, specifically the coupling of the 3D pin-by-pin neutronic solver nTRACER to the sub-channel ...
Papadionysiou Marianna   +6 more
doaj   +1 more source

A SUBCHANNEL COARSENING METHOD FOR Serpent2-SUBCHANFLOW APPLIED TO A FULL-CORE VVER PROBLEM [PDF]

open access: yesEPJ Web of Conferences, 2021
This work presents a methodology to coarsen subchannel models to accelerate largescale Serpent2-SUBCHANFLOW calculations. The method is based on first building a fully detailed subchannel model and then combining subchannels into larger channels with ...
García Manuel   +7 more
doaj   +1 more source

Neutronic calculations for the VVER-1000 MOX core computational benchmark using the OpenMC code [PDF]

open access: yesNuclear Energy and Technology, 2023
The goal of this study is to perform neutronic calculations of the VVER-1000 MOX core computational benchmarks with an OpenMC code along with ENDF/B-VII.1 nuclear data library.
Md Imtiaj Hossain   +3 more
doaj   +3 more sources

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