High Temperature Design and Damage Evaluation of MOD.9Cr-1Mo Steel Heat Exchanger

Author:

Lee Hyeong-Yeon1,Kim Jong-Bum1,Park Hong-Yune2

Affiliation:

1. Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea

2. AD-Solution Co., Ltd., 1101 Hanjin Officetel 535-5, Bongmyoung-dong Yusong-gu, Daejeon 305-301, Republic of Korea

Abstract

High temperature design and evaluation of creep-fatigue damage for sodium-to-sodium heat exchanger, decay heat exchanger (DHX), in a sodium test loop have been conducted. The DHX is a shell- and tube-type heat exchanger with an outer diameter of 21.7 mm and effective length of 1.73 m. The DHX shell and tube materials were Mod.9Cr-1Mo steel. The temperatures of shell inlet and shell outlet in the DHX are 510 °C and 308 °C, respectively, while the temperatures of tube inlet and outlet are 254 °C and 475 °C, respectively. Three-dimensional finite element analysis was conducted for the DHX, and evaluation of creep-fatigue damage at several critical locations of the heat exchanger was carried out according to the elevated temperature design codes of the ASME Section III Subsection NH and RCC-MR. Evaluations on the integrity of the DHX and code comparisons were carried out for the critical locations of the DHX. The evaluation results showed that damages at the tubesheet joints of tube-to-tubesheet and tubesheet-to-shell were not so critical in the present DHX model.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference17 articles.

1. Lee, T. H. , Kim, J. M., Kim, T. J., Eoh, J. H., Lee, Y. B., and Lee, H. Y., 2011, “Design report of STELLA-1,” Report No. KAERI/TR-4295/2011.

2. Construction of a High Temperature Grade 91 Sodium Component Test;Lee;Mater. Sci. Forum

3. Scientific Design of Large Scale Sodium Thermo-Hydraulic Test Facility in KAERI;Lee

4. Creep-Fatigue Damage for a Structure With Dissimilar Metal Welds of Mod 9Cr-1Mo and 316L Stainless Steel;Lee;Int. J. Fatigue

5. Study on Type-IV Damage Prevention in High Temperature Welded Structures of Next-Generation Reactor Plant, Part I Fatigue and Creep-fatigue Behavior of Welded Joints of Mod.9Cr-1Mo Steel;Takahashi

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