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Numerical study on two-phase flow instability in multi-parallel channels of helical-coiled once-through steam generator of lead-cooled fast reactor

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成果类型:
期刊论文
作者:
Qian, Guan-Hua;Zhao, Ya-Nan*;Wang, Xu;Zhao, Peng-Cheng;Xie, Jin-Sen;...
通讯作者:
Zhao, Ya-Nan;Yu, T
作者机构:
[Zhao, Ya-Nan; Xie, Jin-Sen; Yu, Tao; Qian, Guan-Hua; Zhao, YN; Zhao, Peng-Cheng] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China.
[Zhao, Ya-Nan; Xie, Jin-Sen; Qian, Guan-Hua; Zhao, Peng-Cheng; Yu, Tao] Minist Educ, Key Lab Adv Nucl Energy Design & Safety, Hengyang 421001, Hunan, Peoples R China.
[Wang, Xu] China Nucl Engn Consulting Co Ltd, Beijing 100032, Peoples R China.
通讯机构:
[Yu, T ; Zhao, YN] U
Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China.
语种:
英文
关键词:
Helical-coiled once-through steam generator;Multi-parallel channels;Two-phase flow instability;Time-domain analysis
期刊:
Nuclear Engineering and Technology
ISSN:
1738-5733
年:
2024
卷:
56
期:
11
页码:
4895-4904
基金类别:
National Natural Science Foundation of China [11875162, 12205142]; Hunan Provincial Natural Science Foundation of China [2023JJ40526]
机构署名:
本校为第一且通讯机构
院系归属:
核科学技术学院
摘要:
The helical-coiled once-through steam generator (H-OTSG) has the advantages of compact structure and strong heat transfer ability, and is appropriate for lead-cooled fast reactor. The two-phase flow instability may cause mechanical vibration and thermal fatigue of heat transfer tube bundles, posing a serious threat to the safe operation of the H-OTSG. In this work, the secondary side of the H-OTSG characterized as multi-parallel channels is modeled by RELAP5/MOD3.4 code, and the oscillation behavior during start-up and the influence of structural and operating parameters on system stability ar...

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