Development and Validation of Multiscale Coupled Thermal-Hydraulic Code Combining RELAP5 and Fluent Code

In nuclear reactor system research, the multiscale coupled thermal-hydraulic (T-H) system code and CFD code is one of the most prevalent research areas, and it could help improve simulation fidelity and optimize nuclear reactor design. Additionally, a new idea known as the function fitting method (F...

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Bibliographic Details
Main Authors: Lin Sun, Minjun Peng, Genglei Xia, Xuesong Wang, Mingyu Wu
Format: Article
Language:English
Published: Frontiers Media S.A. 2021-02-01
Series:Frontiers in Energy Research
Subjects:
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2020.613852/full

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