The Fusion Materials Irradiation Test (FMIT) facility lithium system - A design and development status

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

OSTI ID:6009441

Brackenbury, P J

The design and development of the Fusion Materials Irradiation Test (FMIT) Facility lithium system is outlined. This unique liquid lithium recirculating system, the largest of its kind in the world, is described with emphasis on the liquid lithium target assembly and other important components necessary to provide lithium flow to the target. The operational status and role of the Experimental Lithium System (ELS) in the design of the FMIT lithium system are discussed. Safety aspects of operating the FMIT lithium system in a highly radioactive condition are described. Potential spillage of the lithium is controlled by cell liners, by argon flood systems and by remote maintenance features. Lithium chemistry is monitored and controlled by a sidestream loop, where impurities measured by instruments are collected by hot and cold traps.

• Research Organization: Westinghouse Hanford Company, P.O. Box 1970, Richland, WA 99352
• OSTI ID: 6009441
• 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
CIRCULATING SYSTEMS
CONTAINMENT
CONTROL SYSTEMS
DESIGN
ELEMENTS
FMIT LINAC
IMPURITIES
LINEAR ACCELERATORS
LITHIUM
METALS
MONITORING
OCCUPATIONAL SAFETY
RADIATION PROTECTION
RADIOACTIVITY
REMOTE HANDLING
REMOVAL
SAFETY
TARGETS
TRAPS