UWFDM-895 Reduced Activation Stainless Steels for Fusion Reactors
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UWFDM-883 Irradiation Behavior of Bonded Structures: Impact of Swelling-Creep-Stress Relationship
Radiation damage will be a major key point in the design of the many duplex components in fusion reactors. There is a substantial amount of available data showing that stress plays a major role in the onset, and possibly the rate, of void growth in austenitic stainless steels. There is also a strong support for models which predict a coupling of swelling and creep through the stress environment...
متن کاملRecent progress of R&D activities on reduced activation ferritic/martensitic steels
Several types of reduced activation ferritic/martensitic (RAFM) steel have been developed over the past 30 years in China, Europe, India, Japan, Russia and the USA for application in ITER test blanket modules (TBMs) and future fusion DEMO and power reactors. The progress has been particularly important during the past few years with evaluation of mechanical properties of these steels before and...
متن کاملCurrent Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy
Reduced-activation ferritic/martensitic (RAF/M) steels have been considered to be the prime candidate for the fusion blanket structural material. The irradiation data obtained up to now indicates rather high feasibility of the steels for application to fusion reactors because of their high resistance to degradation of material performance caused by both the irradiation-induced displacement dama...
متن کاملHigh heat flux testing of 12–14Cr ODS ferritic steels
0022-3115/$ see front matter 2009 Published by doi:10.1016/j.jnucmat.2009.09.022 * Corresponding author. E-mail address: [email protected] (Z. Oksiut The thermal performance of Fe–(12–14)Cr–2W–0.3Ti–0.3Y2O3 ODS reduced activation ferritic steels, which are considered as candidate first wall materials for the future fusion power reactors and were manufactured by mechanical alloying in hydr...
متن کاملUWFDM-1394 Structural Materials Damage in Fusion and Fission Systems
Calculations were performed to quantify the damage parameters in the leading candidate structural and plasma facing materials when used in magnetic and inertial confinement fusion systems and when irradiated in fission reactors. The structural materials considered are ferritic steel, austenitic steel, vanadium alloy and SiC/SiC composite. Plasma facing materials included beryllium, tungsten, an...
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