A Mechanistically-Based Model of Irradiation Damage in Low Alloy Steel Submerged Arc Welds

ASTM Special Technical Publication

Volumn STP 1405, Issue , 2001, Pages 8-27

  Williams, Timothy J ^a   Ellis, David ^a  

^a ROLLS ROYCE PLC   (United Kingdom)

Author keywords

Charpy shift; copper; fracture toughness shift; hardness; Irradiation embrittlement; modelling; nickel; pressure vessel steels; submerged arc weld metal

Indexed keywords

ALLOY STEEL; COPPER; DUCTILE FRACTURE; FRACTURE TOUGHNESS; NEUTRON IRRADIATION; PRESSURE VESSELS; STEEL METALLURGY;

ARC-WELD METALS; CHARPY SHIFT; FRACTURE TOUGHNESS SHIFT; IRRADIATION DAMAGE; IRRADIATION EMBRITTLEMENT; LOW-ALLOY STEEL; MODELING; PRESSURE VESSEL STEELS; SUBMERGED ARC; SUBMERGED ARC WELD METAL;

HARDNESS;

EID: 29144483302     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/STP10522S     Document Type: Conference Paper

References (24)

1. Odette, G. R., "On the Dominant Mechanism of Irradiation Embrittlement of Reactor Pressure Vessel Steels, " Scripta Metallurgies Vol. 17, 1983 pp. 1183-1188.
2. Fisher, S. B., Harbottle, J. E., and Aldridge, N. B., "Radiation Hardening in Magnox Pressure Vessel Steels, " Philosophical Transactions of the Royal Society of London, Vol. A315, 1985, p.310.
3. Lucas, G. E., Odette, G. R., Lombrozo, P. M, and Sheckherd, J. W., "Effects of Composition, Microstructure and Temperature on Irradiation Hardening of Pressure Vessel Steels, " Effects of Radiation on Materials: Twelfth International Symposium.ASTMSTP 870, F. A. Gamer and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia, 1985, pp. 900-930.
4. Odette, G. R., and Lucas, G. E., "Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models and Data Correlations, " Proceedings of the Second IAEA Specialists' Meeting on Irradiation Embrittlement, Vienna, Austria, October 1984, ASTM 1985.
5. Fisher, S. B., and Buswell, J. T., " A Model for PWR Pressure Vessel Embrittlement, " International Journal of Pressure Vessels and Piping, Vol 27, 1987, p.91.
6. , h International Symposium, ASTM STP 1175, A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia, 1993, pp. 424-443.
7. , h International Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996, pp. 25-58.
8. Williams, T. J., Thomas, A. F., Berrisford, R. A., Austin, M., Squires, R. L., and Venables, J. H., "The Influence of Neutron Exposure, Chemical Composition, and Metallurgical Condition on the Irradiation Shift of Reactor Pressure Vessel Steels, " Effects of Radiation on Materials: Eleventh International Symposium, ASTM STP 782, H. R. Brager and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia, PA, 1982, pp. 343-374.
9. Williams, T. J., Ellis, D., Swan, D. I., McGuire, J., Whalley, S. P., English, C. A., Venables, J. H., and de la cour Ray, P. H. N., "The Influence of Copper, Nickel and Irradiation Temperature on the Irradiation Shift of Low Alloy Steels, " Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, TMS AIME/ANS/NACE, September 1985, ANS Illinois, 1986, pp. 393-399.
10. Williams, T. J., Burch, P. R., English, C. A., and de la cour Ray, P. H. N., "The Effect of Irradiation Dose Rate and Temperature, and Copper and Nickel Content, on the Irradiation Shift of Low Alloy Submerged Arc Welds, " Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, TMS/ASM/ANS/NACE, G.J. Theus, J.R. Weeks Eds., August/September 1987, Michigan, 1998, pp.121-131.
11. th International Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing of Materials, West Conshohocken, PA, 1996, pp. 91-205.
12. th International Symposium, ASTM STP 1405, S. T. Rosinski, M. L. Grossbeck, T. R. Allen, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2002 (this volume).
13. Britt and Leuke, "The Estimation of Parameters in Non-Linear Implicit Models, " Technometrics, Vol. 15, No. 2, 1973.
14. Eason, E. D., Wright, J. E., and Odette, G. R., "Improved Embrittlement Correlations for Reactor Pressure Vessel Steels, " NUREG/CR-6551, MCS 970501, November 1998.
15. th International Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996, pp. 103-118.
16. th International Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996, pp. 569-590.
17. Odette, G. R., Lucas, G. E., and Klingensmith, D., "Anomalous Hardening in Model Alloys and Steels Thermally Aged at 290°C and 350°C: Implications to Low Flux Irradiation Embrittlement, " Effects of Irradiation on Materials: 18' International Symposium, ASTMSTP 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1999, pp. 88-101.
18. th International Symposium, ASTMSTP 1175, A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia, PA, 1994, pp. 394-423.
19. Odette, G. R„ Lombrozo, P. M., Wullaert, R. A., "Relationship Between Irradiation Hardening and Embrittlement of Pressure Vessel Steels, " Effects of Radiation on Materials: Twelfth International Symposium, Twelfth International Symposium, ASTMSTP 870, F. A. Garner and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia, 1985, pp. 840-860.
20. Odette, G. R., and Lucas, G. E., "Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models and Data Correlations, " Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume), ASTMSTP 909, L. E. Steele, Ed., American Society for Testing and Materials, Philadelphia 1986, pp. 206-241.
21. Odette, G. R., Lucas, G. E., and Klingensmith, R. D., "The Influence of Metallurgical Variables on the Temperature Dependence of Irradiation Hardening in Pressure Vessel Steels, " Effects of Radiation on Materials: 17' International Symposium, ASTMSTP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996, pp 606-622.
22. Russell, K. C, and Brown, L. M., Acta Metallurgica, Vol. 20, 1972, pp. 969-974.
23. Taylor, L. G., and Williams, T. J., "Validation of Through Life Mechanical Properties of Nuclear Pressure Vessel Steels, " Lifetime Management and Evaluation of Plant, Structures and Components, Dynamic Testing Agency's Fourth International Conference on "Engineering Structural Integrity Assessment, " J. H. Edwards, P. E. J. Flewitt, B. C. Gasper, K. A. McLarty, P. Stanley and B. Tomkins, Eds., Cambridge, UK, September 1998, p 389.
24. English, C. A., IG-RDM: "History and Purpose and Recent Technical Highlights, " IG-RDM8 Open Workshop, Fracture Toughness Master Curve for Reactor Pressure Vessel Steels, Nashville, 1999.