DOI QR코드

DOI QR Code

Aging Evaluation of Duplex Cast Stainless Steel Using Ball Indentation Test

볼 압입시험을 이용한 2상 주조 스테인리스강의 열화 평가

  • Published : 2005.09.01

Abstract

Cast stainless steel (CSS) is thermally aged by a long term exposure in the range of nuclear power plant operating temperature. The thermal aging is a cause of concern for the continued safe and reliable operation of CSS nuclear components. Therefore, an assessment of degradation in material properties of these components has been importantly considered. In this study the ball indentation tests were performed on four cast stainless steels aged at $400^{\circ}C$ for 3600 hours, to investigate the applicability of ball indentation test to the assessment of aging degradation of cast stainless steels. Thus, the reliability of ball indentation test for aged CSS was analyzed by evaluating the scattering of data tested from each material and by comparing tensile properties obtained from ball indentation test and standard tensile test. Also, the tensile properties of aged CSS obtained from ball indentation test were compared with those predicted by the evaluation procedure developed on the basis of material database for aged CSS.

Keywords

References

  1. Pekner, D. and Bernstein, I. M., 1987, HandBook of Stainless Steels, McGraw-Hill Book Company, New York
  2. Shah, V.N. and Macdonald, P.E., 1993, Agine and life Extension of Major Light Water Reactor Components, Elservier Science Pub., Amsterdam
  3. Electric Power Research Instiute, 1998, 'Generic Licence Renewal Technical Issues Summary,' EPRI TR-107521
  4. Chopra, O.K. and Shack, W.J., 1994, Assessmment of Thermal Embrittlement of Cast Stainless steel, NUREG/CR-6177, ANL-94/2
  5. Goto, T., Naito, T. and Yamaoka, T., 1998, 'A study on NDE Method of Thermal Agent of Cast Duplex Stainless Steels,' Mucl. Eng. & Des., Vol.182, pp. 181-192
  6. Cheon, J.S. and Kim, I.S., 2000, 'Evaluation of thermal aging embrittlement in CF8 duplex stainless steel By small punch test,' J. Nucl. Mater., Vol.278, pp.96-103 https://doi.org/10.1016/S0022-3115(99)00213-5
  7. Jang, J.I., Choi, Y., Son, D.I., Lee, Y.H., Kwon, D., Kim, J.T., 2002, 'Determination of New Parameter for Materials Degradation Using Continuous Indention Testing Technique,' Trans. of KSME (A), Vol.26, No. 5, pp. 881-889 https://doi.org/10.3795/KSME-A.2002.26.5.881
  8. Haggag, F.M., 2001, 'In-situ Nondestructive Measurements of Key Mechanical Properties of Oil and Gas Pipelines,' Residual Stress Measurement and General Nondestructive Evaluation, ASME PVP-429, pp.99-104
  9. Murty, K.L., Miraglia, P.Q., Mathew, M.D., Shah, V.N. and Haggag, F.M., 1999, 'Characterization of Gradients in Mechanical Properties of SA-533B Steel Welds Using Ball indentation,' Int. J. of Pres. Ves. & piping, Vol. 79, pp. 361-369 https://doi.org/10.1016/S0308-0161(99)00006-X
  10. Byun, T.S., Kim, J.W. and Hong, J.H., 1998, 'A Theoretical Model for Determination of Fracture Toughness of Reactor Pressure Vessel Steels in the Transition Region from Automated Ball Indention Test,' J. of Nucl. Mater., Vol. 252, pp.187-196 https://doi.org/10.1016/S0022-3115(97)00338-3
  11. Kim, J.W., 2004, 'Evaluation of Tensile Properties of cast stainless Steel Using Ball Indentation Test,' J. Kor. Nucl. Soc., Vol.36, pp.237-247
  12. Ahn, J.H. and Kwon, D., 2000, 'Evauation of Plastic Flow Properties of Materials through the Analysis of Indentation Load-depth Curve,' J. Kor, Inst. Met. & Mater., Vol.38, pp.1606-1611