Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
권호 표지
DOI QR코드

DOI QR Code

Radioactivity Calculation Considering Kori Unit 1 Operation History for the Defected Baffle Former Bolts

고리1호기 가동이력을 고려한 손상 배플포머볼트 방사화 계산

  • Received : 2023.05.25
  • Accepted : 2023.06.19
  • Published : 2023.06.30
Download PDF
⟨ Previous Next ⟩

Abstract

The defected baffle former bolts of Kori unit 1 were withdrawn to analyze the cause of damage and gamma-ray measurement is being scheduled. Prior to that, in order to calculate the specific radioactivity value of the baffle former bolt, a radioactivity calculation method considering the actual operation history of the nuclear power plant is introduced and the calculation results are shown. In particular, the radioactivity calculation method considering the operation history is obtained by defining the monthly contribution factor from the actual monthly operation history. As a result, the results considering operation history are 16-28% lower than the general radioactivity calculation results. These results can contribute to establish a reasonable but economical strategy when planning nuclear power plant decommissioning.

Keywords

Acknowledgement

이 논문은 2019년도 정부(산업통상자원부)의 재원으로 한국에너지기술평가원의 지원을 받아 수행된 연구임(20191510301140, 해체원전 원자로 내부구조물 배플포머볼트 조사유기 응력부식 균열 열화특성 분석기술개발).

References

  1. Oh, S. J., Na, K. H., Lee, C. G., and Maeng, Y. J., 2022, "Mainenance for Removing of Defected Baffle Former Bolts in Kori unit 1," Trans. of the KPVP, pp. 33-34.
  2. John R. Lamarsh, 2001, "Introduction to Nuclear Engineering ," 3rd ed. Chapter 2.
  3. ASTM E 263, "Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron," ASTM International, West Conshohocken, PA.
  4. ASTM E 481, "Standard Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver," ASTM International, West Conshohocken, PA.
  5. ASTM E 844, "Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E706(IIC)," ASTM International, West Conshohocken, PA.
  6. ASME A 240, "Standard Specification for Chromium and Chromium-Nichel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels and for General Applications," ASTM International, West Conshohocken, PA.
  7. Evans, J. C., Lepel, E. L., Sanders, R. W., Wilkerson, C. L., Silker, W., Thomas, C. W., Abel, K. H., and Robertson, D. R., 1984, "Long-Lived Activation Products in Reactor Materials," U.S. Nuclear Regulatory Commission, Washington, DC, NUREG/CR-3474.
  8. RSICC Data Libraty Collection DLC-185, 1996 March, "BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross section Library Drived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications," Oak Ridge National Laboratory.
  9. Westinghouse, 2011, "RAPTOR-M3G Version 2.0 User Manual," Westinghouse, Cranberry, Pittsburgh PA, LTR-REA-11-65, Rev. 0.
  10. Westinghouse, 2018, "Fluence Determination with RAPTOR-M3G and FERRET," Westinghouse Electric Company, Cranberry, Pittsburgh, PA, WCAP-18124-NP-A.