Preliminary Round Robin Test(RRT) for Program for the Inspection of Nickel Alloy Components(PINC) - Reactor Vessel Head Penetration (RVHP) -

다국어 초록 (Multilingual Abstract)

After several PWSCCs were found in Bugey(France), Ringhals(Sweden), Tihange(Belgium), Oconee, Arkansas, Crystal Fever, Davis-Basse, VC Summer(U.S.A.), Thuruga(Japan), USNRC and PNNL started the research on PWSCC, that is, the PINC project. USNRC required KINS to participate in the PINC project in May 2005. KINS organized the Korean consortium at March 2006 and Pre-RRT for RVHP were performed for the preparation of PINC RRT. Through these preliminary RRT, Korea NDE teams can learn and develop the detection and sizing technique for RVHP dissimilar metal weld. These techniques are now being prepared in Korea and need to be utilized for the In-service inspection of the RVHP and BMI of Korea Nuclear Power Plants. PINC RRT mock-ups will be helpful to training.

참고문헌 (Reference)

1 Jenssen, A., "Structural Assessment of Defected Nozzle to Safe-End Welds in Ringhals 3 and 4" SFEN 43-54, 2002

2 Amzallag, C., "Stress Corrosion Life Experience of 182 and 82 Welds in French PWRs" 2002

3 Buisine, D., "Stress Corrosion Cracking in the Vessel Closure Head Penetrations of French PWRs" 1993

4 "Reactor Coolant System Weld Issues"

5 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, "Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors" 2004

6 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, "Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. SUMMER" 2000

7 United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles" 2000

8 Shah, V.N., "Assessment of Pressurized Water Reactor Control Rod Drive Mechanism Nozzle Cracking" prepared for U.S. Nuclear Regulatory Commission, Safety Programs Division 1994

9 Bamford, W., "A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends" 2003