Published October 1998 | Version v1
Journal article

Current status and future R and D for reduced-activation ferritic/martensitic steels

  • 1. JAERI, Ibaraki (Japan). Dept. of Mater. Sci. and Eng.
  • 2. Inst. of Advanced Energy, Kyoto Univ. (Japan)
  • 3. Oak Ridge National Lab., Oak Ridge, TN (United States)
  • 4. Battelle Pacific Northwest Lab., Richland, WA (United States)
  • 5. Consultant, EC/DGXII/Fusion Program, Brussels (Belgium)
  • 6. Inst. fur Materialforschung I, Forschungszentrum, Karlsruhe (Germany)

Description

International research and development programs on reduced-activation ferritic/martensitic steels, the primary candidate-alloys for a DEMO fusion reactor and beyond, are briefly summarized, along with some information on conventional steels. An International Energy Agency (IEA) collaborative test program to determine the feasibility of reduced-activation ferritic/martensitic steels for fusion is in progress and will be completed within this century. Baseline properties including typical irradiation behavior for Fe-(7-9)%Cr reduced-activation ferritic steels are shown. Most of the data are for a heat of modified F82H steel, purchased for the IEA program. Experimental plans to explore possible problems and solutions for fusion devices using ferromagnetic materials are introduced. The preliminary results show that it should be possible to use a ferromagnetic vacuum vessel in tokamak devices. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
258-263
Journal Issue
pt.A
Journal Page Range
p. 193-204
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
8. international conference on fusion reactor materials (ICFRM-8)
Dates
26-31 Oct 1997
Place
Sendai (Japan)

Optional Information

Notes
44 refs.