Results 61 to 70 of about 4,217 (206)
Message passing resource allocation for the uplink of multicarrier systems
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 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
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
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
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
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
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
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
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]
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

