Low-chronium reduced-activation ferritic steels for fusion

Conference · Fri Jan 01 04:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6836133

Klueh, R L; Alexander, D J ^[1]

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1. Oak Ridge National Laboratory, TN (United States)

Ferritic steels are being considered as candidate structural materials for fusion reactors because of their greater swelling resistance, higher thermal conductivity, and lower thermal expansion than austenitic stainless steels. The first ferritic steels considered in the U.S. fusion program were the high-chromium Cr-Mo steels, such as Sandvik HT9 (here designated 12 Cr-1 MoVW) with a nominal composition (all compositions are in weight percent) of Fe-12 Cr-1 Mo-0.25 V-0.5 W-0.5 Ni-0.2 C and the modified 9 Cr-1 Mo steel (designated 9 Cr-1 MoVNb) with nominal composition Fe-9 Cr-1 Mo-0.2 V-0.06 Nb-0.1 C. To a lesser extent, 21 Cr-1 Mo steel (Fe-2.25 Cr-1 Mo-O.1 C) was also considered. Preliminary results indicate that it is possible to develop low-chromium reduced-activation ferritic steels that have tensile and impact properties as good as or better than those of high-chromium steels.

• OSTI ID: 6836133
• Report Number(s): CONF-931160--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480* -- Fusion Technology-- Component Development
ALLOYS
CHROMIUM
ELEMENTS
EXPANSION
FERRITIC STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
METALS
Ma
Materials Studies-- (1992-)
PHYSICAL PROPERTIES
POWER PLANTS
STEELS
SWELLING
TENSILE PROPERTIES
THERMAL CONDUCTIVITY
THERMAL EXPANSION
THERMODYNAMIC PROPERTIES
THERMONUCLEAR POWER PLANTS
THERMONUCLEAR REACTOR MATERIALS
TRANSITION ELEMENTS