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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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  • Creep-fatigue design studies for a sodium-cooled fast reactor with tube sheet-to-shell structure subjected to elevated temperature service
  • Creep-fatigue design studies for a sodium-cooled fast reactor with tube sheet-to-shell structure subjected to elevated temperature service
저자명
Koo. Gyeong-Hoi,Lee. Jae-Han
간행물명
Journal of mechanical science and technology
권/호정보
2010년|24권 3호|pp.711-719 (9 pages)
발행정보
대한기계학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

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.