Published August 1, 2007 | Version v1
Journal article

Recent progress in US-Japan collaborative research on ferritic steels R and D

  • 1. Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)
  • 2. Japan Atomic Energy Research Institute, Tokai, Naka-gun, Ibaraki (Japan)
  • 3. Japan Nuclear Cycle Development Institute, Oarai, Higashiibaraki-gun, Ibaraki (Japan)
  • 4. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
  • 5. University of California at Santa Barbara, Santa Barbara, CA (United States)

Description

The mechanisms of irradiation embrittlement of two Japanese RAFSs were different from each other. The larger DBTT shift observed in F82H is interpreted by means of both hardening effects and a reduction of cleavage fracture stress by M23C6 carbides precipitation along lath block and packet boundaries, while that of JLF-1 is due to only the hardening effect. Dimensional change measurement during in-pile creep tests revealed the creep strain of F82H was limited at 300 deg C. Performance of the weld bond under neutron irradiation will be critical to determine the life time of blanket structural components. Application of the ODS steels, which are resistant to corrosion in supercritical pressurized water, to the water-cooled blanket is essential to increase thermal efficiency of the blanket systems beyond DEMO. The coupling of RAFS and ODS steel could be effective to realize a highly efficient fusion blanket

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2007.03.013;
PII
S0022-3115(07)00339-X;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
367-370
Journal Page Range
p. 60-67
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
12. international conference on fusion reactor materials
Acronym
ICFRM-12
Dates
7-12 Dec 2005
Place
Santa Barbara, CA (United States)

INIS

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.