Design evaluation of serpentine-tube integrated steam generator for sodium-cooled fast reactor

被引：0
|
作者：
Lee, Jewhan [1 ]
Kim, Namhyeong [2 ]
Yoon, Jung [1 ]
Im, Gyeongseo [3 ]
Eoh, Jaehyuk [1 ]
Jo, Hangjin [2 ]
Kim, Hyungmo [3 ]
机构：
[1] Korea Atom Energy Res Inst, 989-111 Daedeok Daero, Daejeon, South Korea
[2] Pohang Univ Sci & Technol, Div Adv Nucl Engn, 77 Cheongam Ro, Pohang, South Korea
[3] Gyeongsang Natl Univ, Sch Mech Engn, 501 Jinju Daero, Jinju, South Korea
来源：
ANNALS OF NUCLEAR ENERGY | 2025年 / 213卷
基金：
新加坡国家研究基金会;
关键词：
Sodium-cooled fast reactor; Serpentine-tube integrated steam generator; Computational fluid dynamics; Heat transfer; Structural integrity; Nuclear reactor safety;
D O I：
10.1016/j.anucene.2024.111133
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The elimination of the intermediate heat transfer system (IHTS) in the sodium-cooled fast reactor (SFR) has long been a goal among researchers, who have extensively developed concepts for simplifying, replacing, or eliminating the IHTS. One such concept involves an integrated steam generator with an additional heat transfer fluid. This paper proposes a heat exchanger with a serpentine-tube arrangement that functions as an integrated steam generator in the primary pool of the SFR. The thermal-hydraulic performance and structural integrity are analyzed, and the transient characteristics under various accident conditions are evaluated. Finally, design improvements are suggested to enhance economic efficiency and applicability by reducing the total volume of hardware.
引用
收藏
页数：17
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