Alloys or metallic compositions – Ferrous – Nine percent or more chromium containing
Patent
1987-02-11
1989-04-04
Yee, Deborah
Alloys or metallic compositions
Ferrous
Nine percent or more chromium containing
148327, 376900, C22C 3844
Patent
active
048184853
ABSTRACT:
An austenitic stainless steel alloy, with improved resistance to radiation-induced swelling and helium embrittlement, and improved resistance to thermal creep at high temperatures, consisting essentially of, by weight percent: from 16 to 18% nickel; from 13 to 17% chromium; from 2 to 3% molybdenum; from 1.5 to 2.5% manganese; from 0.01 to 0.5% silicon; from 0.2 to 0.4% titanium; from 0.1 to 0.2% niobium; from 0.1 to 0.6% vanadium; from 0.06 to 0.12% carbon; from 0.01% to 0.03% nitrogen; from 0.03 to 0.08% phosphorus; from 0.005 to 0.01% boron; and the balance iron, and wherein the alloy may be thermomechanically treated to enhance physical and mechanical properties.
REFERENCES:
patent: 4011133 (1977-03-01), Bloom et al.
patent: 4158606 (1979-06-01), Bloom et al.
Maziasz, "A Perspective on Present and Future Alloy Development . . . ", J. Nucl. Mater., 133 & 134 (1985) pp. 134-140.
Maziasz, "Swelling and Swelling Resistance Possibilities . . . ", J. Nucl. Mater., 122 & 123 (1984) pp. 472-486.
Maziasz, "Microstructural Stability and Control for Improved . . . ", Am. Soc. for Testing & Matls., Phil., PA (1988) pp. 116-161.
Maziasz et al., "Modification of the Grain Boundary Microstructure of the Austenitic PCA Stainless Steel . . . ", J. Nucl. Mater., 141-143 (1986), pp. 973-977.
Maziasz et al., "Microstructural Design of PCA Austenitic . . . ", J. Nucl. Mater. 122 & 123 (1984), pp. 305-310.
Maziasz et al., "Preirradiation Microstructural Development . . . ", J. Nucl. Mater. 103-104 (1981), pp. 797-802.
Maziasz et al., "Application of Quantitative EELS . . . ", 40th Annual EMSA Meeting, G. W. Bailey, Claitor's Publ. Div. (1982) pp. 498-499.
Fujiwara et al., "Development of Modified Type 316 Stainless . . . ", Am. Soc. for Testing & Matls., Phil., PA (1987), pp. 127-145.
Igata et al., "Effects of Nitrogen and Carbon on Void Swelling . . . ", J. Nucl. Mater., 122 & 123 (1984), pp. 219-223.
Swindeman et al., "Residual and Trace Element Effects . . . ", Met. Trans. A, 14A (1983), pp. 581-593.
Rowcliffe et al., Alloy Development for Irradiation Performance Semiannual Progress Report for Period Ending 3/31/84 (DOE/ER-0045/12).
Maziasz, Alloy Development for Irradiation Performance Semiannual Progress Report for Period Ending 9/30/84 (DOE/ER-0045/13).
Rowcliffe et al., An Electron Microscope Investigation of High-Temperature Embrittlement of Irradiated Stainless Steels, pp. 161-199.
Maziasz et al., Preirradiation Microstructural Development Designed to Minimize Properties Degradation During Irradiation in Austenitic.
Kesternich et al., Reduction of Helium Embrittlement in Stainless Steel by Finely Dispersed TiC Precipitates, 104 J. Nucl. Mat'ls. 845.
Maziasz et al., Comparison of 316+Ti with 316 Stainless Steel Irradiated in a Simulated Fusion Environment, Trans. Am. Nucl. Soc.
Martin et al., Solutions to the Problems of High-Temperature Irradiation Embrittlement, Effects of Radiation . . . , ASTM-STP-426.
Braski David N.
Maziasz Philip J.
Rowcliffe Arthur F.
Hamel Stephen D.
Hightower Judson R.
Lovingood Katherine P.
The United States of America as represented by the United States
Yee Deborah
LandOfFree
Radiation resistant austenitic stainless steel alloys does not yet have a rating. At this time, there are no reviews or comments for this patent.
If you have personal experience with Radiation resistant austenitic stainless steel alloys, we encourage you to share that experience with our LandOfFree.com community. Your opinion is very important and Radiation resistant austenitic stainless steel alloys will most certainly appreciate the feedback.
Profile ID: LFUS-PAI-O-178781