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Implementation Status of Performance Demonstration Program for Steam Generator Tubing Analysts in Korea

  • 투고 : 2012.04.14
  • 심사 : 2012.07.13
  • 발행 : 2013.02.28

초록

Some essential components in nuclear power plants are periodically inspected using non-destructive examinations, for example ultrasonic, eddy current and radiographic examinations, in order to determine their integrity. These components include nuclear power plant items such as vessels, containments, piping systems, pumps, valves, tubes and core support structure. Steam generator tubes have an important safety role because they constitute one of the primary barriers between the radioactive and non-radioactive sides of the nuclear power plant. There is potential that if a tube bursts while a plant is operating, radioactivity from the primary coolant system could escape directly to the atmosphere. Therefore, in-service inspections are critical in maintaining steam generator tube integrity. In general, the eddy current testing is widely used for the inspection of steam generator tubes due to its high inspection speed and flaw detectability on non-magnetic tubes. However, it is not easy to analyze correctly eddy current signals because they are influenced by many factors. Therefore, the performance of eddy current data analysts for steam generator tubing should be demonstrated comprehensively. In Korea, the performance of steam generator tubing analysts has been demonstrated using the Qualified Data Analyst program. This paper describes the performance demonstration program for steam generator tubing analysts and its implementation results in Korea. The pass rate of domestic analysts for this program was 71.4%.

키워드

참고문헌

  1. American Society for Nondestructive Testing, Inc., "Personnel Qualification and Certification in Nondestructive Testing," Recommended Practice No. SNT-TC-1A, Columbus, Ohio, USA (1984)
  2. American Society for Nondestructive Testing, Inc., "ASNT Standard for Qualification and Certification of Non- destructive Testing Personnel," ANSI/ASNT CP-189, Columbus, Ohio, USA (1989)
  3. Nuclear Safety and Security Commission, "Regulation on In-service Inspection of Nuclear Facilities," NSSC Notice 2012-10, Korea (2012)
  4. Electric Power Research Institute, "Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 7," EPRI SGMP TR-1013706, Palo Alto, California, USA, pp. G1-G14 (2007)