Published August 1, 2004 | Version v1
Journal article

Recent results of the reduced activation ferritic/martensitic steel development

Description

Significant progress has been achieved in the international research effort on reduced-activation steels. Extensive tensile, fracture toughness, fatigue, and creep properties in unirradiated and irradiated conditions have been performed and evaluated. Since it is not possible to include all work in this limited review, selected areas will be presented to indicate the scope and progress of recent international efforts. These include (1) results from mechanical properties studies that have been combined in databases to determine materials design limits for the preliminary design of an ITER blanket module. (2) Results indicate that the effect of transmutation-produced helium on fracture toughness is smaller than indicated previously. (3) Further efforts to reduce irradiation-induced degradation of fracture toughness. (4) The introduction of a post-irradiation constitutive equation for plastic deformation. (5) The production of ODS steels that have been used to improve high-temperature strength. (6) The method developed to improve fracture toughness of ODS steels

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2004.04.319;
PII
S0022311504001229;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
329-333
Journal Issue
1
Journal Page Range
p. 39-46
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
11. International conference on fusion reactor materials
Acronym
ICFRM-11
Dates
7-12 Dec 2003
Place
Kyoto (Japan)

Optional Information

Copyright
Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.