Cracking in alloy 600/182 reactor vessel head penetrations

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 437, Issue , 2002, Pages 171-178

  Frye, Charles R ^a   Alley, Tom ^a   Arey Jr , Melvin L ^a   Robinson, Michael R ^a  

^a DUKE ENERGY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

REACTOR VESSELS;

BORON; DOSIMETRY; INSPECTION; LEAK DETECTION; NUCLEAR REACTORS; WELDING;

CRACK INITIATION;

EID: 0036385321     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2002-1188     Document Type: Conference Paper

References (5)

1. USNRC Generic Letter (GL) 97-01, "Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations", dated 4/1/1997.
2. th International Conference on NDE in the Nuclear and Pressure Vessel Industries, Stockholm, Sweden, September 1996.
3. Ammirato, F., "Examination of Dissimilar Metal Welds and alloy 600 CRDM Head Penetrations - U.S. Industry Update", Proceedings of SMiRT 16 Workshop, Washington, DC, August 2001.
4. Frye, C., Arey, M., Robinson, M. and Whitaker, D., "Evaluation and Repair of Primary Water Stress Corrosion Cracking In alloy 600/182 Control Rod Drive Mechanism Nozzles", Proceedings of ICONE10, 10TH International Conference on Nuclear Engineering, Arlington, VA, April, 2002.
5. Alley, T., Kietzman, K., and Ammirato, F., "U.S. Industry Activities On Inspection Of CRDM Penetrations", Proceedings of ICONE10, 10TH International Conference on Nuclear Engineering, Arlington, VA, April, 2002.