Published June 1983 | Version v1
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Design of aging-resitant martensitic stainless steels for pressurized water reactors

Description

With the exception of AISI 403 or 410 grades, the use of high strength martensitic stainless steels in PWR is poorly developped because these materials, like ferritic stainless steels, become embrittled by the precitation of a b.c.c. chromium-rich phase during aging at the operating temperature (290 to 3500C). The influence of alloying elements and microstructure on the aging behavior of forged low-carbon martensitic stainless steels containing 12 to 16% Cr, 0 to 2% Mo and 0 to 8% Ni was determined during accelerated aging at 4500C. Quantitative relationships were derived between the maximum increase in hardness, the maximum shift in CVN transition temperature and the chemical composition (Cr, Mo, C) and microstructure

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
FRA--146-3

Conference

Title
Topical conference on ferritic alloys for use in nuclear energy technologies.
Dates
19-23 Jun 1983.
Place
Salt Lake City, CA (USA).