Results 21 to 30 of about 1,620 (263)
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
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
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
Theory of thermal hydraulic quenchback [PDF]
International Journal of Heat and Mass Transfer, 1996 zbMATH Open Web Interface contents unavailable due to conflicting licenses.
Shajii, A., Freidberg, J. P.
openaire +2 more sources
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
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
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
Science and Technology of Nuclear Installations, 2014 To validate the performance and safety of an integral type reactor of SMART, a thermal-hydraulic integral effect test facility, VISTA-ITL, is introduced with a discussion of its scientific design characteristics.
Hyun-Sik Park +5 more
doaj +1 more source
The Best Estimate Plus Uncertainty approach in nuclear reactor safety and licensing: Brief history and the elements after licensing [PDF]
Nuclear Technology and Radiation Protection, 2019 The best estimate plus uncertainty is, at the same time, an approach, a procedure and a frame- work in nuclear thermal-hydraulics and nuclear reactor safety and licensing.
D’Auria Francesco S. +1 more
doaj +1 more source