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Development and validation of an advanced thermal-hydraulic analysis program for helical coil once-through steam generator in lead-based cooled fast reactor

delete2026-06-17
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PRE
AI
Z
Zhipeng Liu
G
Gaoman Zhao
P
Pengrui Qiao
X
Xueyou Ding
Q
Qinglong Wen *
DOI：10.1016/j.pnucene.2026.106499delete
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Abstract

Abstract

En 中文
• An advanced transient analysis code is developed for HCOTSG based on two-fluid model. • The validation of primary side of HCOTSG is done to verify the program. • The steady-state and transient verifications are finished to verify the models. • The program may be useful for the design and safety analysis of HCOTSG.

Journal

Progress in Nuclear Energy cover
Progress in Nuclear Energy
IF:
3.2
Papers:
5.5K
Citations:
10.0K

Organization

C
china institute of atomic energy
Scholars:
589
Papers: 161
Citations: 0
C
chongqing university
Scholars:
1.0W
Papers: 3.9K
Citations: 1
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