TEM (transmission electron microscopy), APFIM (atom-probe field ion microscopy), and SANS (small-angle neutron scattering) examination of aged duplex stainless steel components from some decommissioned reactors

Conference · Fri Jan 01 04:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5622360

Chung, H M; Chopra, O K ^[1]

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1. Argonne National Lab., IL (USA)

Cast stainless steels, composed of duplex phases of austenite and ferrite, are used extensively in nuclear reactors because of their superior strength, weldability, resistance to stress corrosion cracking, and soundness of casting. For example, cast stainless steels are used for primary coiling pipes of pressurized water reactors (PWRs), and valves and pump casings of PWRs and boiling water reactors (BWRs), the structural integrity of which is vital for safe operation of the reactors. In the present investigation, microstructural characteristics of several long-term-aged field components from two decommissioned reactors have been examined by transmission electron microscopy (TEM), atom-probe field ion microscopy (APFIM), and small-angle neutron scattering (SANS) techniques to establish the embrittlement mechanisms for the reactor-aged material. The results have then been compared to those of the laboratory-aged specimens obtained for the temperature range between 300 and 450{degree}C. The chemical compositions and ferrite contents of the reactor components are listed. KRB BWR (located in Gundremmingen, Federal Republic of Germany) had been in service for {approx}12 yr, and the Shippingport PWR (near Pittsburgh, Pennsylvania) had operated for {approx}22 yr.

• OSTI ID: 5622360
• Report Number(s): CONF-880601--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 56
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
AGING
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHROMIUM
CRYSTAL STRUCTURE
ELECTRON MICROSCOPY
ELEMENTS
EMBRITTLEMENT
FERRITIC STEELS
HIGH ALLOY STEELS
ION MICROSCOPY
IRON ALLOYS
IRON BASE ALLOYS
METALS
MICROSCOPY
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
PIPES
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
SCATTERING
SMALL ANGLE SCATTERING
STAINLESS STEELS
STEELS
TRANSITION ELEMENTS
TRANSMISSION ELECTRON MICROSCOPY
WATER COOLED REACTORS
WATER MODERATED REACTORS