Patent Number: 044949871
Section: claims

1. An iron base, gamma prime precipitation hardening austenitic superalloy having improved ductility characteristics after neutron irradiation in a fast breeder nuclear reactor, comprising an iron-nickel-chromium alloy including about 0.05-0.5 weight percent of a ductility enhancing agent selected from the group consisting of yttrium, hafnium and scandium, alone or in combination with each other, titanium and aluminum in amounts effective to produce gamma prime hardening during thermal aging outside of said fast breeder nuclear reactor and silicon in an amount effective through interaction with said ductility enhancing agent to enhance the post neutron irradiation ductility of said alloy. 2. The superalloy according to claim 1 wherein silicon comprises about 0.5 to about 1.5 weight percent of said alloy. 3. The superalloy according to claim 1 or 2 wherein said ductility enhancing agent is yttrium. 4. The superalloy according to claim 1 wherein said alloy contains said gamma prime phase alloy. 5. The superalloy according to claim 2 wherein said alloy contains said gamma prime phase. 6. A gamma prime strengthened austenitic superalloy comprising: about 7-17 weight percent chromium;  about 24-45 weight percent nickel;  about 2-3.8 weight percent titanium;  about 0.5-2.2 weight percent aluminum;  about 0.8-3.5 weight percent molybdenum;  about 0.5-1.5 weight percent silicon;  about 0.03-0.06 weight percent carbon;  about 0.05-0.5 weight percent of an element selected from the group consisting of yttrium, hafnium and scandium, alone or in combination with each other; and  wherein iron is essentially the balance of said gamma prime strengthened austenitic superalloy.  solution treating said superalloy; later aging said superalloy; and  subsequently placing said superalloy in said fast breeder reactor in an aged condition.  cold working said superalloy; and later placing said superalloy in pile in a cold worked condition.  aging said superalloy after said cold working and prior to placing said superalloy in said fast breeder nuclear reactor.  about 25 weight percent Ni;  about 7.5 weight percent Cr;  about 1.0 weight percent Si;  about 1.0 weight percent Mo;  about 0.2 weight percent Mn;  about 0.05 weight percent Zr;  about 3.3 weight percent Ti;  about 1.7 weight percent Al;  about 0.05 weight percent C;  about 0.005 weight percent B;  about 0.2 weight percent of an agent for enhancing the post neutron irradiation ductility of said superalloy after neutron irradiation in a fast breeder reactor selected from the group consisting of Sc, Y, La, and Hf, alone or in combination with each other; and the balance being essentially Fe. 7. The superalloy according to claim 6 further comprising up to about 2 weight percent manganese. 8. The superalloy according to claim 6 wherein said superalloy has improved fast neutron irradiation swelling properties and wherein said element is selected from the group consisting of hafnium and yttrium, alone or in combination with each other. 9. A duct for fuel pins, wherein said duct is comprised of the superalloy according to claim 1, 2 or 6. 10. A fuel pin cladding comprised of the superalloy according to claim 1, 2 or 6. 11. The superalloy according to claim 4, 5 or 6 fabricated by the process comprising the steps of: 12. The superalloy according to claim 1 or 2 fabricated by the process comprising the step of: 13. The superalloy fabricated by the process according to claim 12 further comprising the step of: 14. A gamma prime precipitation hardening austenitic superalloy having the following nominal composition: 15. The alloy according to claim 14 wherein said agent for enhancing post neutron irradiation ductility is selected from the group consisting of Y and Hf. 16. The superalloy according to claim 2 wherein said ductility enhancing agent is scandium. 17. The superalloy according to claim 2 wherein said ductility enhancing agent is hafnium. 18. The superalloy according to claim 6 wherein said element is yttrium. 19. The alloy according to claim 14 wherein said agent for enhancing post neutron irradiation ductility is Y. 20. The alloy according to claim 6 wherein said element is limited to a concentration of about 0.2 to 0.5 weight percent. 21. The alloy according to claim 1 wherein said ductility enhancing agent is limited to a concentration of about 0.2 to 0.5 weight percent. 22. The alloy according to claim 2 wherein said ductility enhancing agent is limited to a concentration of about 0.2 to 0.5 weight percent.