High temperature design of finned-tube sodium-to-air heat exchanger in a sodium test loop-Reference-Cited by-同舟云学术

High temperature design of finned-tube sodium-to-air heat exchanger in a sodium test loop

Published:2013-12 Issue: Volume:265 Page:833-840
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lee Hyeong-Yeon,Eoh Jae-Hyuk,Lee Yong-Bum

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. Scaled Heat Exchanger Design of the Sodium Thermal-Hydraulic Experimental Facility; STELLA-1;Eoh,2010

2. Kim, Y.I, Lee, Y.B., Lee, C.B, Hahn, D.H., 2013. Sodium cooled fast reactor development in Korea, FR-13, 4–7 March, Paris.

3. Lee, T.H., Eoh, J.H., Lee, H.Y. et al. 2009. Scientific design of large scale sodium thermo-hydraulic test facility in KAERI, FR 09, Kyoto, December 7–11, Kyoto, Japan.

4. Preliminary Test Requirements for the Performance Test of Passive Decay Heat Removal System of Sodium-Cooled Fast Reactor, KAERI/TR-3768/2009;Lee,2009

5. Design report of STELLA-1, KAERI/TR-4295/2011;Lee,2011

Cited by 13 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A comprehensive review on the current technologies and recent developments in high-temperature heat exchangers;Renewable and Sustainable Energy Reviews;2023-09

2. Effects of strain rate on the tensile and creep-fatigue properties of 316H stainless steel;International Journal of Pressure Vessels and Piping;2022-12

3. Numerical investigation on fatigue life of aluminum brazing structure with fin-plate-side bar under the low temperature thermal-structure cyclic stress;Engineering Failure Analysis;2022-01

4. Characterizing microstructural evolution and low cycle fatigue behavior of 316H austenitic steel at high-temperatures;Journal of Nuclear Materials;2021-04

5. High-Temperature Design and Integrity Evaluation of a IHX-Combined Steam Generator in Generation IV Reactor;Transactions of the Korean Society of Mechanical Engineers - A;2020-11-30