Results 31 to 40 of about 1,135 (216)

User Clustering and Power Allocation for Energy Efficiency Maximization in Downlink Non-Orthogonal Multiple Access Systems

open access: yesApplied Sciences, 2021
Non-orthogonal multiple access (NOMA) has been considered a promising technique for the fifth generation (5G) mobile communication networks because of its high spectrum efficiency.
Ruibiao Chen   +4 more
doaj   +1 more source

Thermal hydraulic review of light water reactor based on subchannel code CTF [PDF]

open access: yes, 2023
Studying thermal hydraulics in reactor cores is essential for ensuring the safe operation of nuclear power plants and advancing the development of reactors and fuel. In the CASL program initiated by the US Department of Energy, they selected the advanced
Nan Gui (707790)   +5 more
core  

Thermal hydraulic analysis of a PWR loaded with annular fuel rods

open access: yesBrazilian Journal of Radiation Sciences, 2021
In 2006, the final report of the MIT Center for Advanced Nuclear Energy Center the project entitled High Performance Fuel Design for Next Generation PWR’s presented the proposal of an internal and external cooled ring fuel with the objective of ...
Wallen Ferreira De Souza   +3 more
doaj   +1 more source

A Novel Three-Input Field Effect Transistor with Parallel Switching Function Using T-Shaped Channel

open access: yesJournal of Electrical and Computer Engineering, 2022
In this article, a novel three-input field effect transistor with parallel switching function (PSF-TiFET) is proposed. The channels of the new device consist of a vertical subchannel and two horizontal subchannels.
Zening Mo, Zhidi Jiang, Jianping Hu
doaj   +1 more source

Steady-State PWR Core-Wide Analysis Using Subchannel Analysis Method [PDF]

open access: yes, 2010
A subchannel program was designed to make a steady-state core-wide analysis for PWR core. Equations of continuity, energy, axial and transverse momentum, which are the main elements of the program, were presented in the paper.
Xiaoying Zhang, Zhitao Liang
core   +1 more source

Development and Preliminary Validation of Three-dimensional Subchannel Thermal-hydraulic Analysis Code CorTAF for Numerical Reactor Core

open access: yesYuanzineng kexue jishu, 2022
Reactor core is the pivotal component of nuclear power system, and its integrity is an important prerequisite for safe operation of reactor. Traditional nuclear reactor core thermalhydraulic analysis methods cannot meet the high precision simulation ...
LIU Kai;WANG Mingjun;TIAN Wenxi;QIU Suizheng;SU Guanghui
doaj  

Improvement of crossflow model of MULTID component in MARS-KS with inter-channel mixing model for enhancing analysis performance in rod bundle

open access: yesNuclear Engineering and Technology, 2023
MARS-KS, a domestic regulatory confirmatory code of Republic of Korea, had been developed by integrating RELAP5/MOD2 and COBRA-TF. The integration of COBRA-TF allowed to extend the capability of MARS-KS, limited to one-dimensional analysis, to multi ...
Yunseok Lee, Taewan Kim
doaj   +1 more source

Proposal of point-wise power reconstruction for IRT-4M fuel assemblies in coupled Monte-Carlo calculations

open access: yesActa Polytechnica CTU Proceedings, 2022
Current efforts to develop high-fidelity multi-physics tools for research reactors with IRT-4M fuel leads to the involvement of Monte-Carlo transport and subchannel thermo-hydraulic codes in the process of safety assessment.
Pavel Jíška, Jan Frýbort
doaj   +1 more source

THE McSAFE PROJECT - HIGH-PERFORMANCE MONTE CARLO BASED METHODS FOR SAFETY DEMONSTRATION: FROM PROOF OF CONCEPT TO INDUSTRY APPLICATIONS [PDF]

open access: yesEPJ Web of Conferences, 2021
The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap computer power available nowadays e.g. in large HPC. Apart from the classical criticality calculations, the application of Monte Carlo methods for depletion ...
Sanchez-Espinoza V. H.   +5 more
doaj   +1 more source

ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems [PDF]

open access: yes, 2016
Liquid metal cooled fast reactors are promising options for achieving the high degrees of safety and sustainability demanded by the Generation IV paradigm. Among the critical aspects to be addressed in the design process, thermal-hydraulics is one of the
Grasso, G.   +3 more
core   +3 more sources

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