Results 1 to 10 of about 273,037 (331)
Evaluation of DNBR with neutronics calculation in LWR systems [PDF]
Nuclear Energy and Technology, 2023 The heat flux in a Light Water Reactor (LWR) system is used to estimate the Departure from Nucleate Boiling Ratio (DNBR) of the system which is an important thermal hydraulic parameter for nuclear reactors from heat removal point of view.
Suhail Ahmad Khan, Umasankari Kannan
doaj +3 more sources
Thermal-hydraulic calculations of the WWR-SM research reactor [PDF]
Nuclear Physics and Atomic Energy, 2020 The paper presents calculations of the thermal power distribution in the reactor core (RC) of the WWR-SM research nuclear reactor of the Institute of Nuclear Physics of the Academy of Sciences of the Republic of Uzbekistan, settlement Ulugbek, Tashkent, both for all fuel assemblies loaded into the core and for each fuel element of a separate fuel ...
S. A. Baytelesov +2 more
openaire +1 more source
Research on effective temperature calculation method of annular fuel cell
He jishu, 2022 BackgroundThe annular fuel can increase the power density of the reactor due to its double-sided cooling, which is of great significance to the miniaturization and long-life operation of the pressurized water reactor.PurposeThis study aims at the ...
CHEN Zhao +3 more
doaj +1 more source
WHOLE CORE COUPLING METHODOLOGIES WITHIN WIMS [PDF]
EPJ Web of Conferences, 2021 The ANSWERS® WIMS reactor physics code is being developed for whole core multiphysics modelling. The established neutronics capability for lattice calculations has recently been extended to be suitable for whole core modelling of Small Modular Reactors ...
Tollit Brendan +8 more
doaj +1 more source
Design of Cooling Water System (CWS) for CRAFT Lower Hybrid Current Driven (LHCD) System [PDF]
Journal of Applied and Computational Mechanics, 2021 Lower hybrid current driven (LHCD) system, as the most efficient non-inductive current drive method in the tokamak, is an integral part of the Comprehensive Research Facility for Fusion Technology (CRAFT).
Weibao Li +8 more
doaj +1 more source
Frontiers in Energy Research, 2023 The present study focuses on the thermal hydraulic characteristics of fuel assemblies in the China Initiative Accelerator Driven subcritical System (CiADS), which utilizes grid-type spacers to support lead bismuth eutectic (LBE) cooled fast reactors ...
Qi-Jian Chen +8 more
doaj +1 more source
Engineering Science and Technology, an International Journal, 2023 This paper concerns the fluid-thermal characteristics of a high-voltage line-start permanent magnet synchronous motor (LSPMSM). A bidirectional hydraulic-thermal network coupling methodology is proposed and applied to the fluid-thermal characteristics ...
Yongming Xu +3 more
doaj +1 more source
CFD model-based analysis and experimental assessment of key design parameters for an integrated unglazed metallic thermal collector façade [PDF]
, 2020 Active façade systems incorporating solar thermal collectors currently offer very promising energetic solutions. From among the available systems, a simple solution is the unglazed heat collector for potential integration in low-temperature applications.
Blanco, J.M. +3 more
core +1 more source
Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer
Nuclear Engineering and Technology, 2022 s: The research on the flow and heat transfer characteristics of lead bismuth(LBE) is significant for the thermal-hydraulic calculation, safety analysis and practical application of lead-based fast reactors(LFR).
Jie Liu +10 more
doaj +1 more source
Thermal-hydraulic analysis method for the annular fuel structure of lead-bismuth reactor
He jishu, 2021 BackgroundAnnular fuel can significantly increase the power density of the lead-bismuth reactor core, which is of great significance to realize miniaturized design of the reactor and fuel economy improvement.PurposeThis study aims to develop an annular ...
WANG Ting +4 more
doaj +1 more source