THE EXPERIMENTAL DEVELOPMENT OF A FUEL HANDLING SYSTEM FOR THE SODIUM REACTOR EXPERIMENT

Technical Report · Wed Jan 15 04:00:00 EST 1958

OSTI ID:4340412

Hallett, W J; Leppard, J A

A fuel handling system was developed from concepts based on early design studies of Na cooled, graphite moderated reactors. The development program, the evolution of design leading to the construction of the SRE refueling cask and the tests performed on a mock-up of the equipment are described. Because of the conditions encountered, a rather detailed chronological account is given of the experimental development. Emphasis is placed on the difficulties which arose and the specific means utilized to overcome them. The equipment and procedure available at the conclusion of the development effort would permit removal and replacement of a fuel element in the SRE core in about 54 min. The amount of Na carried over by a spent fuel element was found to be between 0.1 and 0.25 pounds. Sodium transferred in the gas phase during the fuel replacement process was found to be of the order of a few micrograms. Reliable provisions were evolved for all steps of the operation, including locating the fuel handling cask, sealing the cask and reactor atmospheres, connecting with the cleaning cell and washing down the removed element. (auth)

• Research Organization: Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
• NSA Number: NSA-12-005002
• OSTI ID: 4340412
• Report Number(s): NAA-SR-2004
• Country of Publication: United States
• Language: English

Related Subjects

CLEANING
FUEL ELEMENTS
GASES
GRAPHITE MODERATOR
HOT CELLS
LIQUID METAL COOLANT
LOSSES
MOCKUP
OPERATION
PHYSICS
RADIATION PROTECTION
REACTOR FUELING
REACTORS
REMOTE HANDLING
SEALS
SHELLS
SODIUM
SRE
TESTING