Remote examination of Fort St. Vrain HTGR fuel and reflector elements

Conference · Sat Dec 31 23:00:00 EST 1983

OSTI ID:6816582

McCord, F; Saurwein, J J

A robotic device developed at GA Technologies was used to perform remote metrological and visual examinations on 105 irradiated fuel and reflector elements removed from the High Temperature Gas Cooled Reactor (HTGR) core of the Fort St. Vrain (FSV) Nuclear Generating Station. All examinations were accomplished in a fraction of the time and at a fraction of the cost for manual methods. Theses examinations have been useful in the verification of core design codes, in monitoring the in-pile performance of graphite blocks, and in qualifying improved core materials.

• Research Organization: GA Technologies, Inc., San Diego, CA (USA)
• DOE Contract Number: AT03-84SF11962
• OSTI ID: 6816582
• Report Number(s): GA-A-17469; CONF-840614-55; ON: DE84012180
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
CONTROL
ENRICHED URANIUM REACTORS
EQUIPMENT
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
NEUTRON REFLECTORS
POST-IRRADIATION EXAMINATION
POWER REACTORS
REACTOR COMPONENTS
REACTORS
REMOTE CONTROL
REMOTE VIEWING EQUIPMENT
SPENT FUEL ELEMENTS
VRAIN REACTOR