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Creep-fatigue design studies for a sodium-cooled fast reactor with tube sheet-to-shell structure subjected to elevated temperature service

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Abstract

In this paper, creep-fatigue damage under elevated temperatures is investigated for a tube sheet-to-shell structure, which is one of the main structures under Gen-IV class 1 components. To do this, detailed step-by-step procedures, including the elastic structural analysis and the ASME-NH code application, are described for a defined representative load cycle. From the sensitivity studies for various design parameters, such as hold time duration, shell thickness, and operating temperature, it is found that a reduction of thickness can decrease the thermal bending stresses, but the negative effect is that it may increase the primary stress and enhance the creep damage. The normal operating temperature is the most significant parameter in the creep-fatigue design.

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References

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Authors and Affiliations

  1. Korea Atomic Energy Research Institute, Gyeongsan, Korea

    Gyeong-Hoi Koo & Jae-Han Lee

Authors
  1. Gyeong-Hoi Koo
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  2. Jae-Han Lee
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Corresponding author

Correspondence to Gyeong-Hoi Koo.

Additional information

This paper was recommended for publication in revised form by Associate Editor Jooho Choi

Gyeong-Hoi Koo received a Ph.D in Mechanical Engineering from KAIST in 1996. He is a principal researcher in KAERI (Korea Atomic Energy Research Institute) since 1989. His expertise in fields of structural engineering are structural vibration, seismic analysis, creep-fatigue design by analysis, buckling analysis, and fatigue monitoring system. Recently he is endorsed as a committee member of ASME Codes and Standards for elevated temperature design for Gen-IV reactors.

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Koo, GH., Lee, JH. Creep-fatigue design studies for a sodium-cooled fast reactor with tube sheet-to-shell structure subjected to elevated temperature service. J Mech Sci Technol 24, 711–719 (2010). https://doi.org/10.1007/s12206-010-0121-1

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  • DOI: https://doi.org/10.1007/s12206-010-0121-1

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