Analysis on thermal hydraulic characteristics for PHENIX natural circulation system using “1D system code + 3D CFD” simulation method
-
Published:2024-11
Issue:
Volume:176
Page:105370
-
ISSN:0149-1970
-
Container-title:Progress in Nuclear Energy
-
language:en
-
Short-container-title:Progress in Nuclear Energy
Author:
Zhao Haiqi,
Zhang YuhaoORCID,
Pu Qifeng,
Song Haijie,
Sui Danting,
Liu Lu,
Lu Daogang
Reference53 articles.
1. CFD Analysis of thermal stratification under PLOFA transient in CLEAR-S;Ali;Prog. Nucl. Energy,2019
2. A summary of sodium-cooled fast reactor development;Aoto;Prog. Nucl. Energy,2014
3. A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method;Cai;Ann. Nucl. Energy,2023
4. Chen, J., Zhang, D., Song, P., et al. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for Sodium Cooled Fast Reactor. Ann. Nucl. Energy, 113, 256-269.
5. Numerical analysis of thermal stratification in the upper plenum of the Monju fast reactor;Choi;Nucl. Eng. Technol.,2013