Crack growth rates of Alloy 600 from the davis-besse reactor CRDM nozzle #3 in PWR environment

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

Volumn 1, Issue , 2005, Pages 171-180

  Chopra, Omesh K ^a   Alexandreanu, Bogdan ^a   Shack, William J ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

DAMAGE ACCUMULATION; ENVIRONMENTALLY ASSISTED CRACKING; REACTOR-VESSEL;

CRACK PROPAGATION; DYNAMIC LOADS; MAGNETIC SUSCEPTIBILITY; MICROSTRUCTURE; PRESSURIZED WATER REACTORS; TENSILE PROPERTIES;

NICKEL ALLOYS;

EID: 29144495637     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2005-71504     Document Type: Conference Paper

References (30)

1. USNRC Information Notice 2002-11, March 12, 2002, "Recent Experience with Degradation of Reactor Pressure Vessel Head."
2. Scott, P., 1991, "An Analysis of Primary Water Stress Corrosion Cracking in PWR Steam Generators," Proc. of the Specialists Meeting on Operating Experience with Steam Generators, Brussels, Belgium, pp. 5-6.
3. Cattant, F., 1997, "Lessons Learnt from the Examination of Tubes Pulled from Electricite de France Steam Generators," Nucl. Eng. Des. 168, pp. 241-253.
4. Diercks, D. R., Shack, W. J., and Muscara, J., 1999, "Overview of Steam Generator Tube Degradation and Integrity Issues," Nucl. Eng. Des. 194, pp. 19-30.
5. USNRC Information Notice No. 1990-10, Feb. 1990, "Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600."
6. USNRC Generic Letter 97-01, April 1, 1977, "Degradation of Control Rod Drive Mechanism and Other Vessel Closure Head Penetrations."
7. Economou, J., Assice, A., Cattant, F., Salin, J., and Stindel, M., 1994, "NDE and Metallurgical Examination of Vessel Head Penetrations," Proc. 3rd Intl. Symp. of Fontevraud, France.
8. Robinson, M. R., April 12, 2001, "Oconee Unit 1 and Unit 3 Reactor Vessel Head Leakage, Cracking of RV Head Penetrations due to Primary Water Stress Corrosion Cracking," presented at the NRC Meeting with the NEI EPRI Material Reliability Program Regarding CRDM Nozzle Crackling Issues, Rockville, MD.
9. Frye, C. R., Alley, T., Arey, Jr., M. L., and Robinson, M. R., 2002, "Cracking in Alloy 600/182 Reactor Vessel Head Penetrations," PVP-Vol. 437, Service Experience and Failure Assessment Applications ASME 2002, P. S. Lam, ed., American Society of Mechanical Engineers, New York, pp. 171-178.
10. USNRC Information Notice 2001-05, April 30, 2001, "Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Driver Mechanism Penetration Nozzle at Oconee Nuclear Station, Unit 3."
11. USNRC Bulletin 2001-01, Aug. 3, 2001, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles."
12. USNRC Information Notice 2000-17, Oct. 18, 2000, "Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. Summer;" Suppl. 1, Nov. 16, 2000;
13. USNRC Information Notice 2000-17, "Crack in weld area of reactor coolant system hot leg piping at V. C. summer;" Suppl. 2, Feb. 28, 2001.
14. Jenssen, A., Norrgard, K., Lagerstrom, J., Embring, G., and Tice, D., 2001, "Assessment of Cracking in Dissimilar Metal Welds," Proc. of the Tenth Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE International, Houston, TX.
15. USNRC Information Notice 2003-11, Aug. 13, 2003, "Leakage Found on- Bottom-Mounted Instrumentation Nozzles;" Suppl. 1, Jan. 8, 2004.
16. USNRC Bulletin 2003-02, Aug. 21, 2003, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity."
17. Ruther, W. E., Soppet, W. K., and Kassner, T. F., 1996, "Corrosion Fatigue of Alloys 600 and 690 in simulated LWR Environments," NUREG/CR-6383, ANL-95/37.
18. Ruther, W. E., Soppet, W. K., and Kassner, T. F., 1998, "Environmentally Assisted Cracking of Alloys 600 and 690 in Simulated LWR Water," in Environmentally Assisted Cracking in Light Water Reactors, Semiannual Report, July 1997-December 1997, NUREG/CR-4667 Vol. 25, ANL-98/30, pp. 42-76.
19. Chopra, O. K., Soppet, W. K., and Shack, W. J., 2001, "Effects of Alloy Chemistry, Cold Work, and Water Chemistry on Corrosion Fatigue and Stress Corrosion Cracking of Nickel Alloys and Welds," NUREG/CR-6721, ANL-01/07.
20. Cassagne, T. B., and Gelpi, A., 1991, "Crack Growth Rate Measurements on Alloy 600 Steam Generator Tubes in Steam and Primary Water," Proc. of the Fifth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, American Nuclear Society, La Grange Park, IL, pp. 518-524.
21. Cassagne, T., Caron, D., Daret, J., and Lefevre, Y., 1999, "Stress Corrosion Crack Growth Rate Measurements in Alloys 600 and 182 in Primary Water Loops under Constant Load," Proc. of the Ninth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, F. P. Ford, S. M. Bruemmer, and G. S. Was, eds., The Minerals, Metals, and Materials Society, Warrendale, PA, pp. 217-224.
22. Magdowski, R., Vaillant, F., Amzallag, C., and Speidel, M. O., 1997 "Stress Corrosion Crack Growth Rates of Alloy 600 in Simulated PWR Coolant," Proc. of the 8th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, S. M. Bruemmer, ed., American Nuclear Society, La Grange Park, IL, pp. 333-338.
23. Le Hong, S., Amzallag, C., and Gelpi, A., 1999, "Modeling of Stress Corrosion Crack Initiation on Alloy 600 in Primary Water of PWRs," Proc. of the Ninth Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, F. P. Ford, S. M. Bruemmer, and G. S. Was, eds., The Minerals, Metals, and Materials Society, Warrendale, PA, pp. 115-122.
24. Vaillant, F., Boursier, J. M., Amzallag, C., Champredonde, J., Daret, J., and Bosch, C., 2003, "Influence of a Cyclic Loading on Crack Growth Rates of Alloy 600 in primary Environment: An Overview," Proc. of the 11th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE International, Houston, TX, pp. 189-198.
25. Ruther, W. E., Soppet, W. K., Kassner, T. F., and Shack, W. J., 1999, "Environmentally Assisted Cracking of Alloys 600 and 690 in Simulated LWR Water," Environmentally Assisted Cracking in Light Water Reactors, Semiannual Report, January 1998-July 1998, NUREG/CR-4667 Vol. 26, ANL-98/18, pp. 25-32.
26. Scott, P. M., 1996, "Prediction of Alloy 600 Component Failures in PWR Systems," Proc. of Corrosion '96 Research Topical Symposia, Part 1 - Life Prediction of Structures subject to Environmental Degradation, NACE, International, Houston, TX, pp. 135-160.
27. Scott, P. M., and Benhamou, C., 2001, "An Overview of Recent Observations and Interpretations of IGSCC in Ni-Base Alloys in PWR Primary Water," Proc. of the 10th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE International, Houston, TX.
28. Amzallag, C., Le Hong, S., Benhamou, C., and Gelpi, A., 2000, "Methodology used to Rank the Stress Corrosion Susceptibility of Alloy 600 PWR Components," PVP Vol. 410-2, Assessment Methodologies for Preventing Failures: Service Experience and Environmental Considerations, Vol. 2, ASME 2000, R. Mohan, ed., American Society of Mechanical Engineers, New York, pp. 163-170.
29. White, G. A., Hickling, J., and Mathews, L. K., 2003, "Crack Growth Rates for Evaluating PWSCC of Thick-Wall Alloy 600 Material," Proc. of the 11th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE International, Houston, TX, pp. 166-179.
30. Chopra, O. K., Gruber, E. E., and. Shack, W. J., 2003, "Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless Steels," NUREG/CR-6826, ANL-03/22.