Title of article
High temperature design of finned-tube sodium-to-air heat exchanger in a sodium test loop
Author/Authors
Lee، نويسنده , , Hyeong-Yeon and Eoh، نويسنده , , Jae Hyuk and Lee، نويسنده , , Yong-Bum، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2013
Pages
8
From page
833
To page
840
Abstract
A sodium test loop called ‘SELFA’ (sodium thermal-hydraulic experiment loop for finned-tube sodium-to-air heat exchanger) for simulating thermal hydraulic behavior of the FHX (finned-tube sodium-to-air heat exchanger) unit in a Korean prototype sodium-cooled fast reactor is planned to be constructed at KAERI (Korea Atomic Energy Research Institute). In this study, the elevated temperature design for a model FHX and creep–fatigue damage evaluation have been conducted for the model according to the design codes of ASME section III subsection NH and RCC-MRx based on full 3D finite element analyses. Design optimization for the finned-tubes and tube arrangements in the scaled-down FHX has been performed. The materials of the FHX and piping systems are austenitic stainless steel type 316. The design temperature of the SELFA test loop is 600 °C and the design pressure is 1 MPa. The damage evaluation results have shown that no creep–fatigue damage occurs in the present design of the FHX under the intended test conditions.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2013
Journal title
Nuclear Engineering and Design Eslah
Record number
1593780
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