Published June 1983
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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.Files
16064790.pdf
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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).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 16064790
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CHEMICAL COMPOSITION; CHROMIUM-NICKEL-MOLYBDENUM STE; DUCTILE-BRITTLE TRANSITIONS; EMBRITTLEMENT; LOW CARBON-HIGH ALLOY STEELS; MARTENSITIC STEELS; MECHANICAL PROPERTIES; MICROSTRUCTURE; PWR TYPE REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; REACTORS; STAINLESS STEELS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS