Transactions of the Korean Society of Mechanical Engineers A (대한기계학회논문집A)

The Korean Society of Mechanical Engineers (대한기계학회)
권호 표지
DOI QR코드

DOI QR Code

High-Temperature Design and Integrity Evaluation of Sodium-Cooled Fast Reactor Decay Heat Exchanger

소듐냉각고속로 붕괴열교환기의 고온 설계 및 건전성 평가

  • Received : 2013.04.12
  • Accepted : 2013.08.25
  • Published : 2013.10.01
Download PDF
⟨ Previous Next ⟩

Abstract

In this study, high temperature design and creep-fatigue damage evaluation of a decay heat exchanger (DHX) in the decay heat removal systems of a sodium-cooled fast reactor (SFR) have been performed. Detail design and 3D finite element analysis have been conducted for the DHXs to be installed in active and passive decay heat removal systems in Korean Generation IV SFR, and the DHX installed in the STELLA-1(Sodium integral effect test loop for safety simulation and assessment) at KAERI (Korea Atomic Energy Research Institute). Evaluations of creep-fatigue damage based on full 3D finite element analyses were conducted for the two Mod.9Cr-1Mo steel heat exchangers according to the elevated temperature design codes of ASME Section III Subsection NH and RCC-MR code. Code comparisons were made based on the creep-fatigue damage evaluation and issues on conservatisms of the design codes were discussed.

본 연구에서는 소듐냉각 고속로 붕괴열교환기(DHX)의 고온 설계 및 크리프-피로 손상 평가를 수행하였다. 제 4 세대 소듐냉각 고속로의 능동 및 피동 잔열제거계통에 설치되는 DHX와 한국원자력연구원의 STELLA-1 시험루프에 설치된 DHX에 대해 상세설계 및 3D 유한요소해석을 수행하고, 동 결과에 기초하여 고온설계 기술기준인 ASME Section III Subsection NH와 RCC-MR 코드를 따라 크리프-피로 손상평가를 수행하였다. 크리프-피로 손상평가 결과에 기초하여 두 설계기준에 대해 비교 분석하고, 설계 기술기준의 보수성 이슈에 대해 토의하였다.

Keywords

References

  1. Kim, Y. I., Jang, J.W., Lee, J.H., Kim, S.J., Kim, S.O., Kim, J. B., Jung, H.Y. and Lee, H.Y., 2012, Conceptual Design Report of SASFR Demonstration Reactor of 600MWe Capacity, KAERI/TR-4598/2012.
  2. Lee, H. Y., Lee, J. H., Lee, T. H., Eoh, J. H., Kim, T. J. and Lee, Y.B., 2010, "Construction of a High Temperature Grade 91 Sodium Component Test," Materials Science Forum, Vols. 416-419, pp. 528-531.
  3. ASME Boiler and Pressure Vessel Code, 2010, Section III, Div. 1, Subsection NH, Class 1 Components in Elevated Temperature Service.
  4. RCC-MRx Subsection B: Class N1RX Reactor Components, Its Auxiliary Systems and Supports, Draft 2010 AFCEN RCC-MRx code, December, 2010.
  5. Lee, H. Y., Kim, J. B. and Park, H. Y., 2012, "Creep- Fatigue Damage Evaluation of Sodium to Air Heat Exchanger in Sodium Test Loop Facility," Nuclear engineering and Design, Vol. 250, pp.308-315. https://doi.org/10.1016/j.nucengdes.2012.05.034
  6. Lee, H. Y., Kim, J. B. and Park, H. Y., 2012, "High Temperature Design and Damage Evaluation of Mod.9Cr-1Mo Steel Heat Exchanger," Journal of Pressure Vessel Technology, Transactions of ASME, Vol. 133, Oct. pp.051101-10.
  7. Lee, H.Y., Eoh, J.H. and Lee, Y.B., 2013, "High- Temperature Design of Sodium-to-Air Heat Exchanger in Sodium Test Loop," Trans. Korean Soc. Mech. Eng. A, Vol. 37, No. 5, pp. 665-671.
  8. Chellapandi,P., R. Srinivasan, Vaze, K.K, Chetal, S.C, Bhoje, S.B., 1989, "Structural Design of the IHX for PFBR," 10th International Conference on Structural Mechanics in Reactor Technology (SMIRT-10), Anaheim, CA, USA, August 14-18.
  9. Lee, H.Y, Eoh, J.H, Lee, Y.B, 2013, "High Temperature Design and Damage Evaluation of a Helical Type Sodium-to-Air Heat Exchanger in a Sodium-Cooled Fast Reactor," Journal of Mechanical Science and Technology, in press, April, 2013.
  10. Eoh, J.H, Lee, H.Y, Kim, T.J, Jeong, J.Y, Lee, Y.B, 2013, "Design Features of a Large-scale Sodium Thermal-hydraulic Test Facility: STELLA," International Conference on Fast Reactors and Related Fuel Cycles, 4-7 March 2013, Paris.
  11. ABAQUS Users manual, 2010, Version 6.10, Dassault Systems, USA.
  12. ASME Code Case N-812, 2010, Alternative Creep- Fatigue Damage Envelope for Grade 91, ASME.