Ferritic steels have been considered candidate structural materials for first wall and blanket structures for fusion power plants since the late 1970s. The first steels considered in the United States were the conventional Cr-Mo steels Sandvik HT9 (nominally 12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C, here designated l2Cr-1MoVW), modified 9Cr-1Mo steel (9Cr-1Mo-0.2V-0.06Nb-0. IC, designated 9Cr-1MoVNb) and, to a lesser extent, 2 1/4Cr-1Mo steel (2.25Cr-Mo-0.1C). All compositions are in wt. %. The normalized-and-tempered 9 and 12Cr steels had a tempered martensite microstructure, and the normalized-and-tempered 2 1/4 Cr steel had a tempered bainite microstructure. This report describes chromium steels tested in normalized and tempered conditions. Miniat...
The thermal performance of Fe-(12-14)Cr-2W-0.3Ti-0.3Y(2)O(3) ODS reduced activation ferritic steels,...
Significant progress has been achieved in the international research effort on reduced activation fe...
Poster presented of: 13th International Workshop on Plasma-Facing Materials and Components for Fusi...
The development of low-activation ferritic/martensitic steels is a key to the achievement of nuclear...
Materials are currently being developed for use in the International Thermonuclear Experimental Reac...
Due to the low neutron-induced radioactivity of their main constituent, two novel Cr-based structura...
Steels are being developed for fusion-reactor applications that contain only elements that produce r...
Ferritic/martensitic steels are candidate structural materials for a DEMO fusion reactor and are inv...
Economic and environmental concerns demand that the power-generation industry seek increased efficie...
The 9Cr and 12Cr martensitic/ferritic steels are candidate first wall and blanket materials for appl...
In this work we have studied brittle fracture in high-chromium reduced activation tempered martensit...
Ferritic martensitic steels show limited swelling and susceptibility to helium effects and can be ma...
AbstractFor improved performance of the components in a fusion reactor, an increased application tem...
Structural components of commercial fusion power plants will be exposed to high fluxes of 14 MeV fus...
This chapter begins with a short overview of the historical development of the ferritic/martensitic ...
The thermal performance of Fe-(12-14)Cr-2W-0.3Ti-0.3Y(2)O(3) ODS reduced activation ferritic steels,...
Significant progress has been achieved in the international research effort on reduced activation fe...
Poster presented of: 13th International Workshop on Plasma-Facing Materials and Components for Fusi...
The development of low-activation ferritic/martensitic steels is a key to the achievement of nuclear...
Materials are currently being developed for use in the International Thermonuclear Experimental Reac...
Due to the low neutron-induced radioactivity of their main constituent, two novel Cr-based structura...
Steels are being developed for fusion-reactor applications that contain only elements that produce r...
Ferritic/martensitic steels are candidate structural materials for a DEMO fusion reactor and are inv...
Economic and environmental concerns demand that the power-generation industry seek increased efficie...
The 9Cr and 12Cr martensitic/ferritic steels are candidate first wall and blanket materials for appl...
In this work we have studied brittle fracture in high-chromium reduced activation tempered martensit...
Ferritic martensitic steels show limited swelling and susceptibility to helium effects and can be ma...
AbstractFor improved performance of the components in a fusion reactor, an increased application tem...
Structural components of commercial fusion power plants will be exposed to high fluxes of 14 MeV fus...
This chapter begins with a short overview of the historical development of the ferritic/martensitic ...
The thermal performance of Fe-(12-14)Cr-2W-0.3Ti-0.3Y(2)O(3) ODS reduced activation ferritic steels,...
Significant progress has been achieved in the international research effort on reduced activation fe...
Poster presented of: 13th International Workshop on Plasma-Facing Materials and Components for Fusi...