Results 21 to 30 of about 10,212 (309)
Post-test simulations for the NACIE-UP benchmark by STH codes [PDF]
, 2019 This paper illustrates the results obtained in the last phase of the NACIE-UP benchmark activity foreseen inside the EU SESAME Project. The purpose of this research activity, performed by system thermal–hydraulic (STH) codes, is finalized to the ...
Barone, G. +9 more
core +2 more sources
NEUTRONIC MODELING STRATEGIES FOR A LIQUID FUEL TRANSIENT CALCULATION [PDF]
EPJ Web of Conferences, 2021 Framework • A detailed and highly flexible numerical tool to study criticality accidents has been developed • The tool implements a Multi-Physics coupling using neutronics, thermal-hydraulics and thermal-mechanics models based on Open FOAM and SERPENT ...
Blanco J.A., Rubiolo P., Dumonteil E.
doaj +1 more source
GEN-IV LFR development: Status & perspectives [PDF]
, 2018 Since Lead-cooled Fast Reactors (LFR) have been conceptualized in the frame of Generation IV International Forum (GIF), great interest has focused on the development and testing of new technologies related to Heavy Liquid Metal (HLM) nuclear reactors. In
Bassini, Serena +6 more
core +1 more source
Phase Distribution for Subcooled Flow Boiling in an Inclined Circular Tube
International Journal of Photoenergy, 2018 An experimental investigation of phase distribution for subcooled flow boiling in an inclined circular tube (i.d. 24 mm) was conducted in this paper.
Wei Bao +5 more
doaj +1 more source
Numerical analysis of temperature stratification in the CIRCE pool facility [PDF]
, 2019 In the framework of Heavy Liquid Metal (HLM) GEN IV Nuclear reactor development, the focus is in the combination of security and performance. Numerical simulations with Computational Fluid Dynamics (CFD) or system codes are useful tools to predict the ...
EDEMETTI, FRANCESCO +5 more
core +1 more source
Experimental Research on Passive Residual Heat Removal System of Chinese Advanced PWR
Science and Technology of Nuclear Installations, 2014 Passive residual heat removal system (PRHRS) for the secondary loop is one of the important features for Chinese advance pressurized water reactor (CAPWR).
Zhuo Wenbin +4 more
doaj +1 more source
Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket
Yuanzineng kexue jishu, 2022 Chinese Fusion Engineering Test Reactor (CFETR) has been proposed to bridge the technology gap between the International Thermonuclear Experimental Reactor (ITER) and the Fusion Demonstration Reactor (DEMO). As the most crucial nuclear component, fusion
DAI Tao;CAO Liangzhi;HE Qingming;WU Hongchun
doaj
DEMO WCLL BB breeding zone cooling system design: analysis and discussion [PDF]
, 2019 The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium self-sufficiency, shielding the Vacuum Vessel and removing the heat generated in the tokamak plasma.
Caruso, Gianfranco +4 more
core +1 more source
Open Research Europe, 2022 The aim of this work is to evaluate three methodologies regarding semi-empirical scroll compressor modeling for different refrigerants and conduct a comparative analysis of their results and accuracy.
George Meramveliotakis +2 more
doaj +1 more source
Nuclear Engineering and Technology, 2018 A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the Primärkreislauf-Versuchsanlage (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project.
Roman Mukin +3 more
doaj +1 more source