Results 51 to 60 of about 308 (180)
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
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
Modernization of the SC-INT subchannel thermal-hydraulic code
The article presents the main results of the work cycle on modernizing the source code of the SC-INT computer program designed for subchannel thermal-hydraulic calculations of the water-cooled nuclear reactors cores. The mathematical description of the program is briefly provided, including the method of allocation of control volumes in space, the ...
Evgeny A. Vertikov +6 more
openaire +2 more sources
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
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
This paper presents a validation study of the subchannel analysis code SLTHEN used for the core thermal-hydraulic design of the Prototype Gen-IV sodium-cooled fast reactor (PGSFR).
Sun Rock Choi +4 more
doaj +1 more source
Understanding interfacial area concentration (IAC) is crucial for analyzing gas–liquid interfacial transfer processes of mass, momentum, and energy. A two‐group IAC model, which considers the dependence of bubble size on two‐phase flow characteristics, has demonstrated outstanding potential in modeling the IAC in dispersed two‐phase flows. Based on the
Meng Yu +4 more
wiley +1 more source
Performance Enhancement of OFDM‐Based Hybrid Multiplexed Ro‐FSO System Under Complex Rain Conditions
The radio over free‐space optical (Ro‐FSO) link serves as an effective and resilient solution for distributing radio frequency (RF) signals over turbulent and adverse weather conditions, using high‐frequency optical carriers. This work proposes an architecture for a high‐speed, spectral‐efficient, and long‐reach hybrid multiplexed Ro‐FSO system that ...
Shivaji Sinha +4 more
wiley +1 more source
Overview of Hybrid Satellite–Terrestrial Networks (HSTNs): Key Technologies and Upcoming Challenges
Hybrid satellite–terrestrial networks (HSTNs) represent a crucial technology in the advancement of next‐generation communication systems, including 6 G. This paper presents an in‐depth review of cooperative and cognitive HSTNs, highlighting the key technologies, system models, and performance metrics that define their operation.
Akbar Asgharzadeh-Bonab +4 more
wiley +1 more source

