Assessment of pneumatic powder transfer for use in fuels refabrication plants

Technical Report · Thu Mar 01 04:00:00 EST 1979

OSTI ID:5916813

Lyon, W L; Larouere, P J

As part of the overall Fuels Refabrication and Development (FRAD) Program being conducted for the US DOE, Westinghouse has completed a task whose objective was to perform an evaluation of the pneumatic transport of nuclear fuel powders. The task included the installation and testing of representative segments of a full scale pneumatic transport system. This report provides conclusions and recommendations based on the results of the test program as well as an assessment of the advantages and disadvantages of the use of pneumatic transport for conveying powders within a commercial mixed oxide fuels refabrication facility. Criteria for the design and operation of systems for the pneumatic transport of mixed oxide powders in commercial mixed oxide fuel fabrication facilities are recommended. One possible disadvantage is the requirement for blowback filters.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Fuel Div.
• OSTI ID: 5916813
• Report Number(s): WCAP-9490
• Country of Publication: United States
• Language: English

Related Subjects

050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
360201 -- Ceramics
Cermets
& Refractories-- Preparation & Fabrication
ACTINIDE COMPOUNDS
CHALCOGENIDES
ENERGY SOURCES
EVALUATION
FEASIBILITY STUDIES
FILTERS
FUEL FABRICATION PLANTS
FUELS
MIXED OXIDE FUEL FABRICATION PLANTS
NUCLEAR FACILITIES
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PNEUMATIC TRANSPORT
POWDERS
REACTOR MATERIALS
TRANSPORT
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES