DOI QR코드

DOI QR Code

Evaluation of Creep-Fatigue Integrity for High Temperature Pressure Vessel in a Sodium Test Loop

소듐 시험루프 내 고온 압력용기의 크리프-피로 건전성 평가

  • Received : 2014.04.21
  • Accepted : 2014.06.05
  • Published : 2014.08.01

Abstract

In this study, high temperature integrity evaluation on a pressure vessel of the expansion tank operating at elevated temperature of $510^{\circ}C$ in the sodium test facility of the SEFLA(Sodium Thermal-hydraulic Experiment Loop for Finned-tube Sodium-to-Air heat exchanger) to be constructed at KAERI has been performed. Evaluations of creep-fatigue damage based on a full 3D finite element analyses were conducted for the expansion tank according to the recent elevated temperature design codes of ASME Section III Subsection NH and French RCC-MRx. It was shown that the expansion tank maintains its integrity under the intended creep-fatigue loads. Quantitative code comparisons were conducted for the pressure vessel of austenitic stainless steel 316L.

Keywords

Creep-Fatigue;Pressure Vessel;Integrity Evaluation;Sodium-Cooled Fast Reactor;Sodium Test Loop

Acknowledgement

Supported by : 미래창조과학부의

References

  1. 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. https://doi.org/10.3795/KSME-A.2013.37.5.665
  2. Lee, H. Y., Eoh, J. H. and 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, Vol. 27, No.9, pp.2729-2735. https://doi.org/10.1007/s12206-013-0718-2
  3. ABAQUS Users Manual, 2010, Version 6.10, Dassault Systems, USA.
  4. 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.
  5. Lee, H. Y., Eoh, J. H. and Lee, Y. B., 2013, "High Temperature Design of Finned-tube Sodium-to-Heat Exchanger in a Sodium Test Loop," Nuclear Engineering and Design, Vol. 265, December 2013, pp.833-840. https://doi.org/10.1016/j.nucengdes.2013.08.073
  6. ASME Boiler and Pressure Vessel Code, Section III, 2013, Rules for Construction of Nuclear Power Plant Components, Div. 1, Subsection NH, Class 1 Components in Elevated Temperature Service, ASME.
  7. RCC-MRx, Section III Subsection B, Class 1 N1RX, 2012, Reactor Components its Auxiliary Systems and Supports, 2012 Edition, AFCEN.
  8. Lee, H. Y., Kim, J. B. and Lee, J. H., 2010, "Construction of a High Temperature Gr.91 Sodium Component Test," Materials Science Forum, Vols.416-419, pp.528-531.
  9. Lee, H. Y., Kim, J. B. and Lee, J. H., 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.
  10. 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, 250, pp.308-315. https://doi.org/10.1016/j.nucengdes.2012.05.034