Automated system for loading nuclear fuel pins

Conference · Sat Oct 01 00:00:00 EDT 1983

OSTI ID:5412263

Marshall, J L

A completely automatic and remotely controlled fuel pin fabrication system is being designed by the Westinghouse Hanford Company. The Pin Operations System will produce fuel pins for the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor Plant (CRBRP). The system will assemble fuel pin components into cladding tubes in a controlled environment. After fuel loading, the pins are filled with helium, the tag gas capsules are inserted, and the top end cap welded. Following welding, the pins are surveyed to assure they are free of contamination and then the pins are helium leak tested.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5412263
• Report Number(s): HEDL-SA-2881-FP; CONF-831047-114; ON: DE84003812
• Resource Relation: Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
FUEL PINS
FFTF REACTOR
FUEL FABRICATION PLANTS
AUTOMATION
LEAK TESTING
WELDING
BREEDER REACTORS
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
JOINING
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUCLEAR FACILITIES
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
050700* - Nuclear Fuels- Fuels Production & Properties
210500 - Power Reactors
Breeding