ML042780451

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Nr Program Papers Release for Unclassified and Unlimited Distribution - Attachment 1
ML042780451
Person / Time
Issue date: 10/13/2004
From: Sheron B
NRC/NRR/ADPT
To: Marion A
Nuclear Energy Institute
Shared Package
ML042780494 List:
References
Download: ML042780451 (15)
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NR PROGRAM PAPERS RELEASED FOR UNCLASSIFIED AND UNLIMITED DISTRIBUTION PRESSURE VESSEL STEEL

1. M. G. Burke, R. J. Stofanak, J. M. Hyde, C. A. English, and W. L. Server, "Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition & Flux Effects,", in Effects of Radiation on Materials, ASTM STP 1447, M. L.

Grossbeck, Ed., American Society for Testing and Materials, West Conshohocken, PA 2002. in press.

2. M. G. Burke, R. J. Stofanak, J. M. Hyde, C. A. English, and W. L. Server, "Irradiation Damage Investigation of A508 Steels:

Ni and Flux Effects" EPRI Workshop on Dose Rate Effects, Lake Tahoe, November 2001.

3. M. G. Burke, R. J. Stofanak, J. M. Hyde, C. A. English, and W. L. Server, "Characterization of Irradiation Damage in A508 Class 2 and Class 4 Forging Steels", in 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. G.S. Was (NACE, 2002). (CD)
4. R. J. Stofanak, Y. Y. Li, M. G. Burke and K. Matuszyk, "Irradiation Embrittlement of High Strength Low Alloy Steels Containing About 3.3% Ni", in 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. G.S. Was (NACE, 2002). (CD)
5. G. L. Wire, W. J. Beggs, and T. R. Leax, "Evaluation of Irradiation Embrittlement A508 Gr 4N and Comparison to Other Low-alloy Steels", Effects of Radiation on Materials, ASTM STP 1447, M. L. Grossbeck, Ed, ASTM International, West Conshohocken, PA, 2003.
6. Y. Y. Li, R. J. Stofanak, and W. J. Beggs, "Charpy Impact Characterization Of The Weld Transition Region Of A High Strength Low Alloy Steel After Irradiation", 11th Int. Conf.

Environmental Degradation of Materials in Nuclear Systems-Water Reactors, ANS, 2003 (CD)

7. Y. Y. Li, "Cessation of Environmentally-Assisted Cracking in a Low-Alloy Steel: Experimental Results", Nuclear Engineering and Design 197 (2000) 45-60.
8. M. G. Burke, M. Watanabe, D. B. Williams and J. M. Hyde, "Irradiation-Induced Development of Nanoscale Features in Steel:

Complementary 3D-APFIM and FEG-STEM Characterization",

Microscopy and Microanalysis, 8 (2002) 292.

Attachment (1)

9. M. K. Miller, P. Pariege and M. G. Burke, "Understanding Pressure Vessel Steels: An Atom Probe Perspective" Materials Characterization, 44 (2000) p. 235.
10. L. A. James, "Fatigue Crack Growth of Low-Alloy Steels in Light Water Reactor Environments", Report No. 1 Environmentally-Assisted Cracking of Ferritic Steels in Aqueous Environments:

An Interpretive Review, WRC Bulletin 404 - August 1995.

11. L. A. James, H. B. Lee, G. L. Wire, "The Effect of Water Flow Rate Upon the Environmentally Assisted Cracking Response of a Low-Alloy Steel": Experimental Results Plus Modeling, Journal of Pressure Vessel Technology, February 1997, Vol. 119 pg. 83
12. G. L. Wire, J. T. Kandra, "Threshold Velocity for Environmentally-Assisted Cracking in Low Alloy Steels",

Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems

- Water Reactors , August 10-14, 1997, Amelia Island Plantation, Amelia Island, Florida.

13. L. A. James, "The Effect of Temperature and Cyclic Frequency Upon Fatigue Crack Growth Behavior of Several Steels in an Elevated Temperature Aqueous Environment", J. Pressure Vessel Technology 116 (2), pg. 122-127, 1994.
14. L. A. James, "Environmentally-Assisted Cracking of Ferritic Steels in Aqueous Environments: an interpretive review, Welding Research Council Bulletin 404, pg. 1-20, 1995.
15. L. A. James and T. J. Poskie, "Correlations Between MnS Area Fraction and EAC Behavior", Technical Report WAPD-T-3012, 1993, DOE Office of Scientific Technical Information, Oak Ridge, TN
16. L. A. James, T. A. Auten, T. J. Poskie, and W. Cullen, "Corrosion Fatigue Crack Growth in Clad Low-Alloy Steels: Part I, Medium-sulfur Forging Steel", J. Press. Vessel Technol, August 1997, Vol. 119, pg. 249-254, 1996.
17. Y. Y Li, 1997, "Cessation of Environmentally Assisted Cracking in a Low-Alloy Steel: Experimental Results", WAPD-T-3127, DOE Office of Scientific Technical Information, Oak Ridge, TN (presented at the 1997 ASME Pressure Vessel and Piping conference, 27-31, July 1997, Orlando, FL Attachment (1) 2
18. G. L. Wire and Y. Y. Li, "Initiation of Environmentally-Assisted Cracking in Low-Alloy Steels", Press. Vessel Pip. 323, 269-289, 1996,
19. G. L. Wire, "Cessation of Environmentally-Assisted Cracking in a Low-Alloy Steel: Theoretical Analysis", Nuclear Engineering and Design 197 (2000) 25-44
20. T. A. Auten, S. Z. Hayden and R. H. Emanuelson, "Fatigue Crack Growth Rate Studies of Medium Sulfur Low Alloy Steels Tested in High Temperature Water", Proceedings of the Sixth International Conference on the Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, San Diego, CA, August 1993, TMS Publication, RE Gold and EP Simonen, Eds
21. T. A. Auten, B. D. Macdonald, D. W. Scavone and D. Bozik, "J-Integral Characterization of the Nozzle Steels from Intermediate Test Vessels IV-5 and IV-9", 25th National Symposium on Fracture Mechanics, ASTM Committee E-8, Bethlehem, PA, June 28, 1993, Published in ASTM 25th Vol., Fracture Mechanics, American Society for Testing and Materials, Philadelphia, PA, August 1995.
22. T. A. Auten and W. Yang, "Measurements of Manganese Sulfides in Medium Sulfur Steels with PRC Software Driving an Electron Microprobe ", Presentation made at The Manganese Sulfide Workshop, a limited international meeting held at the BWXT Alliance Research Center, August 9, 1993.
23. T. A. Auten and J. V. Monter, "Temperature and Environmentally Assisted Cracking in Low Alloy Steel",

Proceedings of the 7th International Conference on the Environmental Degradation of Materials in Nuclear Power Systems, Breckenridge, CO, August, 1995

24. D. B. Knorr, "An Evaluation of Temper Embrittlement in A508 Grade 4N Steel", from Proceedings of the Ninth International Symposium on the Environmental Degradations of Materials in Nuclear Power Systems, Newport Beach, CA, 1999, page 845.

LOW STRENGTH NICKEL BASED ALLOYS

25. W.J. Mills, C.M. Brown and M. G. Burke, "Effect of Microstructure on Low Temperature Cracking Behavior of EN82H Welds" in 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. G.S. Was (NACE, 2002). (CD)

Attachment (1) 3

26. W. J. Mills, C. M. Brown and M. G. Burke, "Fracture Behavior of Alloy 600, Alloy 690 EN82H Weld and EN52 Weld in Water" EPRI 2000 Workshop on PWSCC of Alloy 600 in PWRs (Feb.,

2000).

27. D. M. Symons, M. G. Burke and J. P. Foster, "The Relationship Between Stress Corrosion Cracking Fracture Morphology and Microstructure in Alloy 600 " in Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors, ed. (ANS, 1997) p. 237.
28. M. G. Burke and D. M. Symons, "Microstructural Effects on Alloy 600 PWSCC" in Proceedings of the 4th EPRI Workshop on PWSCC of Alloy 600 in PWRs - Daytona Beach, EPRI Report EPRI TR-109138 (1997) E3-1.
29. W. J. Mills and C. M. Brown, "Fracture Toughness of Alloy 600 and an EN82H Weld in Air and Water," Metallurgical and Materials Transactions A, 32A (2001) p. 1161.
30. C. M. Brown and W. J. Mills, "Fracture Toughness of Alloy 690 and an EN52 Welds in Air and Water," Metallurgical and Materials Transactions A, 33A (2002) p. 1725.
31. M. M. Hall, Jr. and D. M. Symons, "Hydrogen Assisted Creep Fracture Model for Low Potential Stress corrosion Cracking in Ni-Cr-Fe Alloys", Symposium on Chemistry and Electrochemistry of Corrosion and Stress Corrosion Cracking: A Symposium Honoring the Contributions of R. W. Staehle, (New Orleans, LA: TMS, 2001), 447-466.
32. M. M. Hall, Jr. and D. M. Symons, "Constitutive Deformation Model For Analysis Of Stress Corrosion Crack Tip Strain Rates In Ni-Cr-Fe Alloy 600", International Conference on Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions, Moran, WY, 2002,TMS/ASM.
33. M. M. Hall, Jr., W. M. Moshier and D. J. Paraventi, "HACF Model Predictions for the Sensitivities of Alloy 600 LPSCC to Stress, Temperature, Carbon Concentration, Cold Work, and Crack Growth Orientation", 2003 NRC Meeting on Reactor Head Penetrations, OCT 2003.
34. P.L. Charpentier, "Experimental Method to Assess the Role of Loading History on Stress Corrosion Cracking", B-T-3497, Eleventh International Conference on Environment\al Degradation Attachment (1) 4

of Materials in Nuclear Power Systems - Water Reactors, ANS, Stevenson, WA, August 2003.

35. M. G. Burke, W. C. Moshier, G. J. C. Carpenter and M. W.

Phaneuf, "Characterization of Intergranular Fracture in a Ni-Cr-Fe Alloy using SEM, FIB and AEM Techniques", Microscopy and Microanalysis, 9 (2004) in press.

36. M. G. Burke, P.T. Duda, G. Botton and M.W. Phaneuf, "Assessment of Deformation using the Focused Ion Beam Technique" Microscopy & Microanalysis, 6 (2000) p. 530.
37. M. G. Burke, B.Z. Hyatt and G. McMahon "SIMS/AEM Characterization of Banded Microstructures in an Ni-Cr-Fe Alloy" in Microscopy & Microanalysis, 5 (1999) p. 862.
38. M. G. Burke, R. J. Wehrer and C. M. Brown, "Real-World Microscopy: Understanding the Environment-Sensitive Behavior of Ni-Base Welds" Microscopy & Microanalysis, 4 (2) (1998) p. 528.
39. M. G. Burke and D. M. Symons, "Microstructural Effects of the SCC Morphology of Alloy 600 in Deaerated Water" Microscopy &

Microanalysis, 3 (2) (1997) p. 783.

40. D. M. Symons, M. G. Burke and J. P. Foster "The Relationship Between Stress Corrosion Cracking Fracture Morphology and Microstructure in Alloy 600 ", in Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors, ed. (ANS, 1997) p. 237.
41. W. J. Mills and C. M. Brown, "Fracture Behavior of Nickel-Based Alloys in Water," 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, 1999, pp. 167-174.
42. W. J. Mills and C. M. Brown, "Stress Corrosion Crack Growth Rates for Alloy 82H Welds in High Temperature Water," Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, 2003.

(CD)

43. D. S. Morton and M. Hanson, "The Effect of pH on Nickel Alloy SCC and Corrosion Performance", Corrosion 2003 Annual (NACE) Conference, March 2003.
44. S. A. Attanasio and D. S. Morton, "Measurement of the Nickel/Nickel Oxide Transition in Ni-Cr-Fe Alloys and Updated Attachment (1) 5

Data and Correlations to Quantify the Effect of Aqueous Hydrogen on Primary Water SCC", Proceedings of the Eleventh International Conference on the Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Stevenson, WA, August 2003.

45. G. A. Young Jr., R. Najafabadi, W. Strohmayer, D. G.

Baldrey, and W. L. Hamm, "An Atomistic Modeling Study of Alloying Element, Impurity Element, and Transmutation Products on the Cohesion of a Nickel 25 {001} Twist Grain Boundary",

Proceedings of the Eleventh International Conference on the Environmental Degradation of Materials in Nuclear Power Systems

- Water Reactors, Stevenson, WA, August 2003.

46. S. A. Attanasio, J. V. Mullen, J. W. Wuthrich, W. W.

Wilkening, and D. S. Morton, "Stress Corrosion Crack Growth Rates (SCCGRs) of Alloy 182 and 82 Weld Metal", Proceedings of the Conference on Vessel Head Penetration Inspection, Cracking, and Repair, Sponsored by the NRC and ANL, Gaithersburg, MD, October 2003.

47. G. A. Young, N. Lewis, and D. S. Morton, "The Stress Corrosion Crack Growth Rate of Alloy 600 Heat Affected Zones Exposed to High Purity Water", Proceedings of the Conference on Vessel Head Penetration Inspection, Cracking, and Repair, Sponsored by the NRC and ANL, Gaithersburg, MD, October 2003.
48. G. A. Young, C. K. Battige, N. Lewis and M. A. Penik "Factors Affecting the Hydrogen Embrittlement Resistance of Ni-Cr-Nb Welds", Sixth International Conference on Trends in Welding Research, Pine Mt., GA, April 2002.
49. G. A. Young, N. Lewis, C. K. Battige, R. A. Somers and M.

A. Penik, "Quantification of Residual Plastic Strains in Ni-Cr-Nb GTAW Welds via Electron Backscatter Diffraction", Sixth International Conference on Trends in Welding Research, Pine Mt., GA, April 2002.

50. S. A. Attanasio, D. S. Morton and M. A. Ando, "Measurement and Calculation of Electrochemical Potentials in Hydrogenated High Temperature Water, including an Evaluation of the Yttria-Stabilized Zirconia/Iron-Iron Oxide (Fe/Fe3O4) Probe as a Reference Electrode", CORROSION/2002, Paper No. 517, 2002
51. S. A. Attanasio, N. Lewis, G. A. Young and D. S. Morton, "Application of Cross-Sectional Analytical Electron Microscopy Attachment (1) 6

to Stress Corrosion Cracking in Nuclear Systems", Spring TMS/ASM Symposium, April 2002.

52. S. A. Attanasio, D. S. Morton and M. A. Ando, "Evaluation of the Yttria-Stabilized Zirconia/Iron-Iron Oxide Probe as a Primary Water Reference Electrode", TMS/ASM Poster Symposium, November 2002.
53. N. Lewis, S. A. Attanasio, D. S. Morton and G. A. Young, "Stress Corrosion Crack Growth Rate Testing and Analytical Electron Microscopy of Alloy 600 as a Function of Pourbaix Space and Microstructure", from Chemistry and Electrochemistry of Corrosion and Stress Corrosion Cracking: A Symposium Honoring the Contributions of RW Staehle, The Materials Society (TMS),

New Orleans, LA, February 11-15, 2001, page 421.

54. S. A. Attanasio, D. S. Morton, M. A. Ando, N. F. Panayotou and C. D. Thompson, "Measurement of the Nickel/Nickel Oxide Phase Transition in High Temperature Hydrogenated Water Using the Contact Electric Resistance (CER) Technique", from Proceedings of the Tenth International Symposium on the Environmental Degradations of Materials in Nuclear Power Systems, Lake Tahoe, NV, August 2001.
55. D. S. Morton, S. A. Attanasio and G. A. Young, "Primary Water SCC Understanding and Characterization Through Fundamental Testing in the Vicinity of the Nickel/Nickel Oxide Phase Transition", from Proceedings of the Tenth International Symposium on the Environmental Degradations of Materials in Nuclear Power Systems, Lake Tahoe, NV, August 2001.
56. D. S. Morton, S. A. Attanasio, G. A. Young, P. L. Andresen and T. M. Angeliu, "The Influence of Dissolved Hydrogen on Nickel Alloy SCC: A Window to Fundamental Insight",

CORROSION/2001, Paper No. 117, 2001.

57. D. S. Morton, S. A. Attanasio, J. S. Fish and M. K.

Schurman, "Influence of Dissolved Hydrogen on Nickel Alloy SCC in High Temperature Water", CORROSION/99, Paper No. 447, 1999.

58. S. A. Attanasio, J. S. Fish, W. W. Wilkening, P. M.

Rosecrans, D. S. Morton, G. S. Was and Y. Yi, "Measurement of the Fundamental Parameters for the Film-Rupture/Oxidation Mechanism - The Effect of Chromium", from Proceedings of the Ninth International Symposium on the Environmental Degradations of Materials in Nuclear Power Systems, Newport Beach, CA, 1999, page 49.

Attachment (1) 7

59. Y. Yi, G. S. Was, J. Cookson, J. S. Fish, S. A. Attanasio, H. T. Krasodomski and W. W. Wilkening, "Creep of Nickel Base Alloys in High Temperature Water", from Proceedings of the Ninth International Symposium on the Environmental Degradations of Materials in Nuclear Power Systems, Newport Beach, CA, 1999, page 269.
60. A. J. Silvia, C. K. McDonald, J. M. Kikel, G. A. Young, C.

K. Battige, N. Lewis, M. A. Penik, "Factors Affecting the Hydrogen Embrittlement Resistance of Ni-Cr-Nb Welds" from proceedings of Sixth International Conference on Trends in Welding Research, Oine Mountain GA, 2002.

61. J. M. Kikel, D. M. Parker, "Ductility Dip Cracking Susceptibility of Inconel Filler Metals 52 and Inconel Alloy 690", Proceedings from Fifth International Conference in Welding Research, Pine Mountain, GA, 1998.
62. M. J. Cola, W. Kroenke, I. Singh, "Analytical Prediction of the Location of Ductility-Dip Cracking in the Trans-Varestraint Test", Proceedings of Fifth International Conference on Residual Stresses, Linkoping, Sweden, June 1997.
63. M. J. Cola, J. M. Kikel, J. T. Salkin, " Narrow Groove Welding on Inconel Alloy 690", Proceedings from 7 8 th Annual American Welding Society Conference, Los Angeles, CA, April 1997.
64. W. Lin, M. J. Cola, " Weldability of Inconel Filler Metal 52"., proceedings of 7 8 th Annual American Welding Society Convention, Los Angeles, CA, April 1997.
65. M. J. Cola, "Ductility Dip Cracking of Inconel Filler Metals", Sixth International Symposium in Physical Simulation, Columbus, Oh, June 1996.

HIGH STRENGTH NICKEL BASED ALLOYS

66. R. Bajaj, W. J. Mills, B. F. Kammenzind and M. G. Burke, "Effects of Neutron Irradiation on Mechanical Behavior of Nickel-Base Fastener Alloys", in Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors, eds. S.

Bruemmer, F.P. Ford, and G. Was (TMS, 2000) p. 1069.

67. W. J. Mills, M. R. Lebo, R. Bajaj, J. J. Kearns, R. C.

Hoffman and J. J. Korinko, "Irradiation Assisted Stress Attachment (1) 8

Corrosion Cracking of HTH Alloy X-750 and Alloy 625," WAPD-T-3034, March 1994, presented at 1994 Meeting of the International Collaborative Group on Irradiation-Assisted Stress Corrosion Cracking (ICGIASCC), March 30-April 1, 1994, Stevenson, WA.

68. M. G. Burke and M. K. Miller, "The Application of Analytical Electron Microscopy and Atom Probe Field-Ion Microscopy to the Analysis of Precipitation Behavior in Alloy 718" 2nd IUMAS Conference: Microbeam Analysis 2000 (Institute of Physics, 2000) p. 161.
69. M. G; Burke and R. Bajaj, "Radiation-Induced Microstructural Changes in Alloy X-750" Electron Microscopy 1998: Proceedings of ICEM XIV vol. 2 eds. H. A. Caleron Benavides and M.J. Yacaman (Inst. of Physics, 1998) p.65.
70. W. J. Mills, M. R. Lebo, J. J. Kearns, R. C. Hoffman, J. J.

Korinko, R. F. Luther and G. B. Sykes, "Effect of Irradiation on the Stress Corrosion Cracking Behavior of Alloy X-750 and Alloy 625," , 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, 1993, pp. 633-643.

71. R. Bajaj, W. J. Mills, M. R. Lebo, B. Z. Hyatt and M. G.

Burke, "Irradiation-Assisted Stress Corrosion Cracking of HTH Alloy X-750 and Alloy 625," 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, 1995, pp. 1093-1107.

72. W. J. Mills, M. R. Lebo and J. J. Kearns, "Inhibition of Stress Corrosion Cracking of Alloy X-750 by Prestrain," 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 1997, pp. 465-474.
73. W. J. Mills, M. R. Lebo and J. J. Kearns, "Hydrogen Embrittlement, Grain Boundary Segregation, and Stress Corrosion Cracking of Alloy X-750 in Low- and High-Temperature Water,"

Metallurgical and Materials Transactions A, Vol. 30A, 1999, pp.

1579-1596.

74. M. G. Burke, W. J. Mills and R. Bajaj, "Microstructure and Properties of Direct-Aged Alloy 625," 5th International Symposium on Superalloys 718, 625, 706 and Various Derivatives, TMS, 2001, pp. 389-398.

Attachment (1) 9

75. W. J. Mills and C. M. Brown, "Fatigue Fracture Surface Morphology for Alloy 718," Superalloys 718, 625, 706 and Various Derivatives, TMS, 2001, pp. 511-522.
76. A. R. Kephart and S. Z. Hayden, "Benefits of Thread Rolling Process to the Stress Corrosion Resistance and Fatigue Resistance of High Strength Fasteners", Proceedings of the Sixth International Conference on the Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, San Diego, CA, August 1993.
77. A. R. Kephart, "Optimum Thread Rolling Process That Improves Stress Corrosion Cracking (SCC) Resistance", ASTM E08 Committee Workshop on Environmental Effects on Structural Integrity of Fasteners, Pittsburgh PA, May 2002.
78. A. R. Kephart, "Fatigue Acceptance Test Limit Criteria for Larger Diameter Rolled Fasteners", ASTM 2nd Symposium on Structural Integrity of Fasteners, Seattle, WA, May 19, 1999, Published in ASTM STP 1391, P M Toor, Ed., American Society for Testing and Materials, Philadelphia, PA, July 2000.

78a. C. M. Brown and W. J. Mills, "Fracture Toughness, Tensile and Stress Corrosion Cracking Properties of Alloy 600, Alloy 690 and Their Welds in Water," Corrosion 96, NACE (1996), Paper No.

90.

78b. W.C. Moshier and C.M. Brown, "Effects of Cold Work and Processing Orientation on Stress Corrosion Cracking Behavior of Alloy 600," CORROSION 56(3), 307 (2000).

78c. L.A. James and W.C. Moshier, "The Effect of Potential on the High-Temperature Fatigue Crack Growth Response of Low Alloy Steels, Part 1: Crack Growth Results," CORROSION SCIENCE 41, 372 (1999).

78d. W.C. Moshier and L.A. James, "The Effect of Potential on the High-Temperature Fatigue Crack Growth Response of Low Alloy Steels, Part 2: Sulfide-Potential Interaction," CORROSION SCIENCE 41, 372 (1999).

STAINLESS STEEL

79. G. L. Wire and W. J. Mills, "Fatigue Crack Propagation from Notched Specimens of 304 Stainless Steel in An Elevated Temperature Aqueous Environment", PVP-Vol. 439, Pressure Vessel and Piping Codes and Standards-2002, PVP2002-1232, ASME, pp 151-64, 2002.

Attachment (1) 10

80. W. M. Evans and G. L. Wire, "Fatigue Crack Propagation Behavior of 304 Stainless Steel from Compact Tension Specimens in an Elevated Temperature Aqueous Environment", PVP-Vol. 439, Pressure Vessel and Piping Codes and Standards-2002, PVP2002-1226, ASME, pp 91-98, 2002.
81. M. G. Burke and N.T. Nuhfer, "Phase Transformations in an Austenitic Stainless Steel Weld During Post-Weld Heat Treatment" Microscopy and Microanalysis, 7 (2001) p. 548.
82. R. A. Gross-Gourley, I.L.W. Wilson, D. W. Pratt, J. A.

Lewis, "Vacuum Brazing of CA6NM Components" Proceedings of Second International Brazing and Soldering Conference, February 2003.

CORE MATERIALS

83. B. F. Kammenzind, "The Influence of In-Situ Clad Straining on the Corrosion of Zircaloy in a PWR Environment" ASTM Symposium on Zirconium in the Nuclear Industry, 2002
84. R. Bajaj, "Effects of Neutron Irradiation on the Microstructure of Alpha Annealed Zircaloy-4", ASTM Symposium on Zirconium in the Nuclear Industry, 2002
85. B. F. Kamenzind, "The Long Range Migration of Hydrogen Through Zircaloy in Response to Tensile and Compressive Stress Gradients", ASTM Symposium on Zirconium in the Nuclear Industry, 2000
86. E. Hillner, "The Corrosion of Zircaloy-Clad Fuel Assemblies in a Geological Repository Environment, WAPD-T-3173, 1998
87. B. F. Kammenzind, "Hydrogen Pickup and Redistribution in Alpha Annealed Zircaloy-4", Zirconium in the Nuclear Industry:

Eleventh International Symposium, ASTM STP 1295, 1996.

88. P. H. Kreyns, Embrittlement of Reactor Core Materials, Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, 1996
89. D. M. Rishel, "The Corrosion Behavior of Hafnium in High-Temperature Water Environments," Journal of Nuclear Materials (2002)

Attachment (1) 11

90. R. Baranwal, M. G. Burke and M. W. Phaneuf, "FIB Microscopy of Oxide Dispersion Strengthened Mo" Microscopy and Microanalysis, 9 (2004) in press.
91. R. Baranwal and M. G. Burke, "Transmission Electron Microscopy of Oxide Dispersion Strengthened (ODS) Molybdenum:

Effects of Irradiation on Microstructure", Phil. Mag., in press (2003).

OTHER

92. T. L. Jungling, D. R. Rauth, D. Goldberg, "Evaluation of Replacement Thread Lubricants for Red Lead and Graphite in Mineral Oil", WPAD-QES-ME-1206, June 1997, Released through DoD-DTIC and DOE-Office of Science and Technical Information
93. C. E. Jordan and A. R. Marder, Lehigh Univ., Bethlehem, PA.

"The Effect of Iron Oxide as an Inhibitation Layer on Iron-Zinc Reactions during Hot-Dip Galvanizing", Metallurgical and Materials Transactions B, Vol. 28B, April 1998, pp 478 - 484.

94. C. E. Jordan and A. R. Marder, Lehigh Univ., Bethlehem, PA, "Fe-Zn phase formation in interstitial-free steels hot-dip galvanized at 450 0 C, Part I - 0.00 wt% Al-Zn baths", Journal of Materials Science, Vol. 32 (1997) 5593 - 5602, Chapman & Hall.
95. C. E. Jordan and A. R. Marder, Lehigh Univ., Bethlehem, PA.

"Fe-Zn phase formation in interstitial-free steels hot-dip galvanized at 450 0 C, Part II - 0.20 wt% Al-Zn baths", Journal of Materials Science, Vol. 32 (1997) 5602 - 5610, Chapman & Hall.

96. C. E. Jordan, R. Zuhr and A. R. Marder, Lehigh Univ.,

Bethlehem, PA. "Effect of Phosphorus Surface Segregation on Iron-Zinc Reaction Kinetics during Hot-Dip Galvanizing",

Metallurgical and Materials Transactions A, Vol 28A, December 1997, pp 2695 - 2703.

97. C. E. Jordan and A. R. Marder, Lehigh Univ., Bethlehem, PA.

"Effect of Substrate Grain Size on Iron-Zinc Reaction Kinetics during Hot-Dip Galvanizing", Metallurgical and Materials Transactions A, Vol 28A, December 1997, pp 2683 - 2694.

98. C. E. Jordan, R.K. Rasefske and A. Castagna, "Thermal Stability of High Temperature Structural Alloys", Long Term Stability of High Temperature Materials, GE Fuchs, KA Danneman and TC Deragon, Eds., TMS Publication, Warrendale, PA, 1999, pp. 55 Attachment (1) 12

SECONDARY PLANT MATERIALS

99. SA Shei & WJ Yang, "Stress Corrosion Crack Tip Microstructure in Nickel-Base Alloys," Corrosion/1994 paper.

100. F. D. Miller, "Monitoring Crack Tip Chemistry by Raman Spectroscopy During Active Crack Growth at Elevated Temperatures

- Factors Influencing Crack Tip Chemistry," Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 10-14, 2003, Stevenson Washington.

101. R. E. Hermer, R. J. Blasi, D. Moran, and C. D. Shaffer, The Use of Raman Spectroscopy for High Temperature Bulk and Surface Chemistry Studies of Alloy 600 in Aqueous Solutions,"

EPRI Surface Chemistry Workshop, Myrtle Beach, 1996.

102. Baum, Allen, "Limits To Crevice Concentration Processes -

With Application To Lead," EPRI/Argonne Heated Crevice Seminar, October 2002.

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Attachment (1) 14

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Attachment (1) 15

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