DOI QR코드

DOI QR Code

Experience in Visual Testing of the Main Feed Water Piping Weld for Hanul Unit 3

한울 3호기 주급수 배관 용접부 육안검사 경험

  • 윤병식 (한국수력원자력 중앙연구원) ;
  • 문균영 (한국수력원자력 중앙연구원) ;
  • 김용식 (한국수력원자력 중앙연구원)
  • Received : 2015.06.12
  • Accepted : 2015.06.23
  • Published : 2015.06.30

Abstract

Nuclear power plant steam generator that is one of the main component has several thousands of thin tubes. And the steam generator tube is subject to damage because of the severe operation conditions such as the high temperature and pressure. Therefore periodic inspections are conducted to ensure the integrity of steam generator component. Hanul unit 3 also has been inspected in accordance with in-service inspection program and is scheduled to be replaced for exceeding the plugging rate which was recommended by manufacturer. During the steam generator replacement activity, we found several clustered porosity on inner surface of main feed water pipe. Additionally crack-like indications were found at weld interface between base material and weld of main feed water pipe. This paper describes the field experience and visual testing results for inner surface of main feed water pipes. The destructive test result had shown that these indications were porosities which were caused by manufacturing process not by operation service.

Keywords

References

  1. Yoon, B.S, Kim, Y.S, Lee, H. and Lee, Y.H, 2006, "Study on Quantitative Flaw Evaluation of Nuclear Power Plant Steam Generator Tube by Ultrasonic Testing" Journal of the Korean Society for Nondestructive Testing Vol. 26, No. 1, pp. 12-17.
  2. American Society of Mechanical Engineering, 1995, ASME Boiler and Pressure Vessel Code, Section XI, New York, pp. 120-159
  3. M. W. Allgaier and P. Mclntire, 1993, "Nondestructive Testing Handbook : Visual Testing", ASNT, Vol. 8, pp. 245-276