Corrosion behaviour of materials selected for FMIT lithium system

Conference · Thu Sep 01 04:00:00 EDT 1983 · Nucl. Technol./Fusion; (United States)

OSTI ID:6294403

Bazinet, G D; Brehm, W F

The corrosion behavior of selected materials in a liquid lithium environment was studied in support of system and component designs for the Fusion Materials Irradiation Test (FMIT) Facility. Testing conditions ranged from about 3700 to about6500 hours of exposure to flowing lithium at temperatures from 230/sup 0/ to 270/sup 0/C and static lithium at temperatures from 200/sup 0/ to 500/sup 0/C. Principal areas of investigation included lithium corrosion/erosion effects on FMIT lithium system baseline and candidate materials. Material coupons and full-size prototypic components were evaluated to determine corrosion rates, fatigue crack growth rates, structural compatibility, and component acceptability for the lithium system. Based on the results of these studies, concerns regarding system materials and component designs were satisfactorily resolved to support a 20-year design life requirement for the FMIT lithium system.

• Research Organization: Westinghouse Kanford Company, P.O. Box 1970, Richland, WA 99352
• OSTI ID: 6294403
• Report Number(s): CONF-830406-
• Conference Information: Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACCELERATORS
ALKALI METALS
CHEMICAL REACTIONS
CORROSION
CORROSION FATIGUE
CORROSIVE EFFECTS
CRACK PROPAGATION
ELEMENTS
FATIGUE
FMIT LINAC
HIGH TEMPERATURE
LINEAR ACCELERATORS
LITHIUM
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
METALS
SERVICE LIFE
TESTING
THERMONUCLEAR REACTOR MATERIALS