Mechanical Properties of Four 7-9%Cr Reduced Activation Martensitic Steels after 2.5 dpa, 300°C Irradiation /

Mechanical Properties of Four 7-9%Cr Reduced Activation Martensitic Steels after 2.5 dpa, 300°C Irradiation /

Reduced Activation Ferritic/Martensitic alloys are being developed for application in future thermonuclear fusion reactors. The behavior of the reduced activation martensitic steel F82H-mod was compared with small amounts of related alloys JLF-1, JLF-1B and ORNL-9Cr2WVTa, following irradiation in th...

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Bibliographic Details
Main Authors: van Osch, E. (Author), Horsten, M. (Author), Lucas, GE (Author), Odette, GR (Author)
Corporate Authors: ASTM International, American Society for Testing and Materials
Format: Book
Language:English
Published: West Conshohocken, Pa. : ASTM International, 2000
Subjects:
Charpy impact behavior
Ductility
Embrittlement
Ferritic-martensitic 7-9%Cr steels
Fracture toughness
Hardening
Low activation
Neutron irradiation
Nuclear pressure vessels > Congresses
Nuclear pressure vessels
Steel > Effect of radiation on > Congresses
Steel > Effect of radiation on
Tensile properties

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