Computer control of fuel handling activities at FFTF

Conference · Fri Mar 01 00:00:00 EST 1985

OSTI ID:5580728

Romrell, D M

The Fast Flux Test Facility near Richland, Washington, utilizes computer control for reactor refueling and other related core component handling and processing tasks. The computer controlled tasks described in this paper include core component transfers within the reactor vessel, core component transfers into and out of the reactor vessel, remote duct measurements of irradiated core components, remote duct cutting, and finally, transferring irradiated components out of the reactor containment building for off-site shipments or to long term storage. 3 refs., 16 figs.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5580728
• Report Number(s): HEDL-SA-3283-FP; CONF-850903-5; ON: DE85008496
• Resource Relation: Conference: International topical meeting on computer applications for nuclear power plant operation and control, Pasco, WA, USA, 8 Sep 1985
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
REACTOR CHARGING MACHINES
REMOTE HANDLING EQUIPMENT
CAMAC SYSTEM
COMPUTERS
DUCTS
FUEL ASSEMBLIES
FUEL CHANNELS
ON-LINE CONTROL SYSTEMS
POST-IRRADIATION EXAMINATION
PROCESS COMPUTERS
REACTOR FUELING
CONTROL SYSTEMS
EPITHERMAL REACTORS
EQUIPMENT
FAST REACTORS
LIQUID METAL COOLED REACTORS
MATERIALS HANDLING EQUIPMENT
ON-LINE SYSTEMS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors