Results 61 to 70 of about 4,217 (206)

Message passing resource allocation for the uplink of multicarrier systems

open access: yes, 2008
We propose a novel distributed resource allocation scheme for the up-link of a cellular multi-carrier system based on the message passing (MP) algorithm.
Abrardo, Andrea   +2 more
core   +1 more source

In‐Depth Numerical Elucidation on Thermal‐Hydraulic Phenomena for EBR‐II XX09 Subassembly During SHRT‐45 Experiment by 1D MARS‐LMR Code and 3D CFD Code

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
In this study, the EBR‐II SHRT‐45 test, simulating a loss‐of‐flow accident without scram, was employed to evaluate the stability and thermal‐hydraulic behavior of the reactor’s fuel assembly cladding. By integrating high‐fidelity computational fluid dynamics (CFD) models with the MARS‐LMR code, this research aims to validate predictive capabilities and
Junbeom Park   +3 more
wiley   +1 more source

Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
A neutronics/thermal‐hydraulics (TH) coupled spatial dynamics code, reactor system transient analysis‐three dimensional (RESTA‐3D), has been developed for both static and transient analysis of large advanced light water reactors (LWRs), with a focus on control rod (CR) ejection accidents.
Yong Cui   +4 more
wiley   +1 more source

Multiphysics Analysis of Natural Circulation‐Driven Operation of Passive Molten Salt Fast Reactor and Effect of Guide Structure

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
A new molten salt reactor (MSR) design has been developed aiming for long‐term operation and high safety. In order to enhance the integrity and economy of the system during the long‐term operation, pumps were removed from the primary system, and the fuel salt flow was developed by natural circulation.
Juhyeong Lee   +5 more
wiley   +1 more source

Validation of the subchannel code LINDEN for void fraction simulation based on the NUPEC PWR tests (PSBT)

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology
Subchannel analysis code is one of the most important thermal-hydraulic analysis tools for nuclear reactor cores. A new subchannel analysis code for PWRs named LINDEN code has been developed by China Nuclear Power Technology Research Institute (CNPRI ...
Yuanbing Zhu, Ke Wang, Ting Wang
doaj   +1 more source

Development and Assessment of Multiphase Sub-channel Code of COSINE

open access: yesYuanzineng kexue jishu, 2022
COSINE software package provides various functions in thermal-hydraulic analysis of pressurized water reactor (PWR) after years of development. In order to meet the engineering design and safety analysis requirements of the advanced passive reactor ...
CHEN Lin;ZHANG Hao;CHENG Yixuan;GUO Yingran;MA Qichao;ZHOU Fanfan;YANG Yanhua;ZHAO Meng
doaj  

Achieving Secrecy Capacity of the Gaussian Wiretap Channel with Polar Lattices

open access: yes, 2017
In this work, an explicit wiretap coding scheme based on polar lattices is proposed to achieve the secrecy capacity of the additive white Gaussian noise (AWGN) wiretap channel.
Ling, Cong, Liu, Ling, Yan, Yanfei
core   +1 more source

Assessment of the Drift‐Flux Parameter Correlations Implemented in the Nuclear Thermal‐Hydraulic Analysis Code TRACE

open access: yesInternational Journal of Energy Research, Volume 2025, Issue 1, 2025.
The present study assessed the drift‐flux parameter correlations implemented in the TRACE code, the flagship thermal‐hydraulic analysis code developed by the United States Nuclear Regulatory Commission (US NRC). The code is architected on the basis of a two‐fluid model.
Takashi Hibiki   +2 more
wiley   +1 more source

Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method

open access: yesNuclear Engineering and Technology, 2020
Subchannel code is one of the effective simulation tools for thermal-hydraulic analysis in nuclear reactor core. In order to reduce the computational cost and improve the calculation efficiency, empirical correlation of turbulent mixing coefficient is ...
Haoran Ju   +7 more
doaj   +1 more source

A new low-cost discrete bit loading using greedy power allocation [PDF]

open access: yes, 2009
In this paper we consider a low cost bit loading based on the greedy power allocation (GPA). Compared to the standard GPA, which is optimal in terms of maximising the data throughput, three suboptimal schemes are suggested, which perform GPA on subsets ...
Alhanafy, W.E.A.E., Weiss, S.
core  

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