Published 1994 | Version v1
Report Open

Fracture toughness of irradiated candidate materials for ITER first wall/blanket structures

  • 1. Oak Ridge National Lab., TN (United States)
  • 2. Japan Atomic Energy Research Inst., Tokyo (Japan)

Description

Disk compact specimens of candidate materials for first wall/blanket structures in ITER have been irradiated to damage levels of about 3 dpa at nominal irradiation temperatures of either 90 or 250 degrees C. These specimens have been tested over a temperature range from 20 to 250 degrees C to determine J-integral values and tearing moduli. The results show that irradiation at these temperatures reduces the fracture toughness of austenitic stainless steels, but the toughness remains quite high. The toughness decreases as the test temperature increases. Irradiation at 250 degrees C is more damaging than at 90 degrees C, causing larger decreases in the fracture toughness. Ferritic-martensitic steels are embrittled by the irradiation, and show the lowest toughness at room temperature

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96004387; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
30 p.
Report number
CONF-940657--9

Conference

Title
17. symposium on effects of radiation on materials.
Dates
20-23 Jun 1994.
Place
Sun Valley, ID (United States).

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400
Funding organization
USDOE, Washington, DC (United States).