Results 21 to 30 of about 5,620 (304)

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

PERSPECTIVES IN SYSTEM THERMAL-HYDRAULICS [PDF]

Nuclear Engineering and Technology, 2012
The paper deals with three main topics: a) the definition of System Thermal-Hydraulics (SYS TH), b) a historical outline for SYS TH and, c) the description of elements for reflection when planning research projects or improvement activities, this last topic being the main reason for the paper.
openaire   +2 more sources

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, Huang Yanping, Xiao Zejun, Peng Chuanxin, Lu Sansan   +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  

Methods based on a semi-empirical model for simulating scroll compressors with HFC and HFO refrigerants [version 2; peer review: 1 approved, 2 approved with reservations]

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, Sotirios Karellas, George Kosmadakis   +2 more
doaj   +1 more source

The MOOSE Thermal Hydraulics Module

Journal of Open Source Software
<p>This archive is created for publication of the Thermal Hydraulics module of the <a href="https://github.com/idaholab/moose">MOOSE framework</a>.
Joshua Hansel, David Andrs, Lise Charlot, Guillaume Giudicelli   +3 more
openaire   +2 more sources

Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE

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, Ivor Clifford, Omar Zerkak, Hakim Ferroukhi   +3 more
doaj   +1 more source

Hydraulic and thermal characterization of a family of thermo-hydraulic separators

Applied Thermal Engineering, 2020
Thermal-hydraulic separators (or hydraulic dispatchers) are flow collectors of relatively small size, connecting two or more hydraulic networks; they are mainly used to reduce the hydraulic interference of primary (e.g. heat supply) and secondary (e.g. heat consumer) circuits, thereby simplifying the system analysis, saving energy and operating complex
Toneatti, Luca, Piller, Marzio, Pozzetto, Dario, Padoano, Elio, Boscolo, Marco   +4 more
openaire   +2 more sources

Methods based on a semi-empirical model for simulating scroll compressors with HFC and HFO refrigerants [version 3; peer review: 3 approved]

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, Sotirios Karellas, George Kosmadakis   +2 more
doaj   +1 more source

Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test

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, Byung-Yeon Min, Youn-Gyu Jung, Yong-Cheol Shin, Yung-Joo Ko, Sung-Jae Yi   +5 more
doaj   +1 more source