대표어
한국학술지인용색인(NRF)
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초록보기
After several damages by PWSCC were found in the world, USNRC and PNNL(Pacific Northwest National Laboratory) started the research on PWSCC under the project name of PINC. The aim of the project was 1) to fabricate representative NDE mock-ups with flaws to simulate PWSCCs, 2) to identify and quantitatively assess NDE methods for accurately detecting, sizing and characterizing PWSCCs, 3) to document the range of locations and morphologies of PWSCCs and 4) to incorporate results with other results of ongoing PWSCC research programs, as appropriate. Korea nuclear industries have also been participating in the project. Thermally and mechanically cracked-four mockups were prepared and phased array and manual ultrasonic testing(UT) techniques were applied. The results and lessons learned from the preliminary RRT are summarized as follows: 1) Korea RRT teams performed the RRT successfully. 2) Crack detection probability of the participating organizations was an average 87%, 80% and 80% respectively. 3) RMS error of the crack sizing showed comparatively good results. 4) The lessons learned may be helpful to perform the PINC RRT and PSI /ISI in Korea in the future.
권호기사
참고문헌 (9건) : 자료제공( 네이버학술정보 )
| 번호 | 참고문헌 | 국회도서관 소장유무 |
|---|---|---|
| 1 | NRC Information Notice 2000-17 (2000) Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. SUMMER, United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation | 미소장 |
| 2 | NRC Information Notice 2004-11 (2006) Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle, United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation | 미소장 |
| 3 | USNRC Website http://www.nrc.gov/reactors/operating/ops-experience/pressure-boundary-integrity/weld-issues/index.html, Reactor Coolant System Weld Issues | 미소장 |
| 4 | Amzallag, C. et al. (2002) Stress Corrosion Life Experience of 182 and 82 Welds in French PWRs, Proceedings Fontevraud International Symposium Number 5 | 미소장 |
| 5 | Bamford, W. and Hall, J. (2003) A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends, 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors | 미소장 |
| 6 | Buisine, D. et al. (1993) Stress Corrosion Cracking in the Vessel Closure Head Penetrations of French PWRs, Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors | 미소장 |
| 7 | Jenssen, A. et al. (2002) Structural Assessment of Defected Nozzle to Safe-End Welds in Ringhals 3 and 4, Proceedings of Fontevraud V International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, SFEN, pp. 43-54 | 미소장 |
| 8 | Shah, V. N. et al. (1994) Assessment of Pressurized Water Reactor Control Rod Drive Mechanism Nozzle Cracking, prepared for U.S. Nuclear Regulatory Commission, Safety Programs Division, NUREG/CR-6245, EGG-2715 | 미소장 |
| 9 | Thomas, L. E. et al. (2003) High-Resolution Analytical Electron Microscopy Characterization of Environmentally Assiasted Cracks in Alloy 182 Weldments, Proceedings of 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Waster Reactros, ANS | 미소장 |
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