Cracking of alloy 600 nozzles and welds in PWRs: Review of cracking events and repair service experience

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Volumn , Issue , 2005, Pages 959-966

  Bamford, Warren ^a   Hall, John ^a  

^a NONE

Author keywords

Alloy 182; Alloy 600; PWSCC; Stress Corrosion Cracking

Indexed keywords

COOLANTS; CORROSION RESISTANT ALLOYS; HEAT TREATMENT; NOZZLES; PIPING SYSTEMS; STEAM GENERATORS; STRESS CORROSION CRACKING; WELDS;

ALLOY 182; ALLOY 600; LOOP PIPING; PRESSURE BOUNDARY RELOCATIONS; PRIMARY COOLANT LEAKAGE;

PRESSURIZED WATER REACTORS;

EID: 33745184657     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (6)

1. W.H. Bamford and J.F. Hall, "A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends," in Proceedings Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems. The Minerals, Metals and Materials Society, 2003.
2. "Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-Wall Alloy 600 Materials," EPRI Report MRP 55, Rev. 1, November 2002.
3. "Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds," EPRI Report MRP 115, November 2004.
4. W.H. Bamford, W. Gahwiller, L. Spain, and J. Lareau, "The Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations, and its Application at North Anna Unit 2," in Flaw Evaluation. Service Experience, and Reliability, ASME PVP Vol. 463, July 2003.
5. C. Amzallag, J. M. Boursier, C. Pages, and C. Gimond, "Stress Corrosion Life Experience of 182 and 82 Welds in French PWRs, in Proceedings Fontevraud International Symposium Number 5," September 2002.
6. W.H. Bamford, et al., "Development of the Technical Basis for Plant Startup for the V.C. Summer Nuclear Plant", ASME PVP Vol. 427, 2001.