Journal
TRANSACTIONS OF THE INDIAN INSTITUTE OF METALS
Volume 62, Issue 2, Pages 81-87Publisher
SPRINGER INDIA
DOI: 10.1007/s12666-009-0011-3
Keywords
ferritic/martensitic steels; creep; elevated temperature strength; Gen IV; thermo mechanical treatment
Categories
Ask authors/readers for more resources
Design concepts for the next generation of nuclear power reactors include water-cooled, gas-cooled, and liquid-metal-cooled reactors. Reactor conditions for several designs offer challenges for engineers and designers concerning which structural and cladding materials to use. Depending on operating conditions, some designs favor elevated-temperature ferritic/martensitic steels for in-core and out-of core applications. Such steels have been investigated in previous work on international fast reactor and fusion reactor research programs. Steels from these fission and fusion programs will provide reference materials for future fission applications. In addition, new elevated-temperature steels have been developed in recent years for conventional power systems that also need to be considered.
Authors
I am an author on this paper
Click your name to claim this paper and add it to your profile.
Reviews
Recommended
No Data Available