MOLTEN-SALT REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1958

Technical Report · Wed Sep 24 04:00:00 EDT 1958

DOI:https://doi.org/10.2172/4291713· OSTI ID:4291713

Reactor Design Studies. A conceptual design of a tworegion, fluid-fuel power reactor, 640 Mwh and 250 Mwe, was prepared and evaluated for fabricability. Design work for the reactor fuel pump was completed. Nuclear calculations were continued with studies of Pu/sup 239/ and U/sup 233/ fuels. Studies of various cover gases indicate only argon and helium are suitable. Test rigs were designed for experimental studies of bearings for molten salt applications. Somc preliminary results are given on both bearings and lubricants. Test of mechanical joints for remote separation of fused salt system components were continued. None of the joints tested gave evidence of leakage. Data from heat transfer coefficient tests on BeF/sub 2/-- LiF-- UF/sub 4/ systems are presented. Physical property measurements were made on BeF/sub 2/-- LiF-- UF/sub 4/ and BeF/ sub 2/--NaF -- UF/sub 4/ systems. A conceptual design was prepared of a 5 Mw experimental reactor in which molten salt fuel would be circulated by thermal convection. The beat exchanger equipment required for gas cooling a molten-- salt reactor was studied. Materials Studies. Metallurgical examinations and corrosion evaluations were made of specimens of several Inconel and INR-8 thermal- convection loops in which various fluoride mixtures had been circulated. Specimens of Inconel and INOR-8 exposed to a sodium-- graphite system were examined for carburization effects to their physical properties. Brazing alloys with high gold and silver contents show promising corrosion resisthnce to molten salts. Additional tests indicate the weldability of INOR-8 is satisfactory. INOR-8 and Inconel capsules were fabricated for testing the stability of graphite in contact with molten-salt fuels. Phase equilibrium studies of BeF/sub 2/-- LiF systems containing UF/sub 4/ and/or ThF/sub 4/ were continued. Data were obtained on the solubility of PuF/sub 3/, NiF/sub 3/, noble gases, and various fission products in alkali fluoride-- beryllium fluoride systems. The chemical reactions of BeO with fluoride melts were investigated. Data are also presented on Cr diffusion in Ni-base alloys and CrF--BeF/sub 2/ vapor pressures. (For preceding period see ORNL-2474.) (D.E.B.)

• Research Organization: Oak Ridge National Lab., Tenn.
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-12-016695
• OSTI ID: 4291713
• Report Number(s): ORNL-2551
• Country of Publication: United States
• Language: English

Related Subjects

ALKALOIDS
ALUMINUM ALLOYS
ARGON
BEARINGS
BERYLLIUM FLUORIDES
BERYLLIUM OXIDES
BRAZING
CARBIDES
CHEMICAL REACTIONS
CHROMIUM
CHROMIUM ALLOYS
CHROMIUM FLUORIDES
CONFIGURATION- - CONVECTION
COOLANT LOOPS
CORROSION
CORROSION PROTECTION
DIFFUSION
FABRICATION
FAILURES
FISSION PRODUCTS
FLUORIDES
FUELS
FUSED SALT FUEL
FUSED SALTS
GAS COOLANT
GOLD
GRAPHITE
HEAT EXCHANGERS
HEAT TRANSFER
HELIUM
INERT GASES
JOINTS
LEAKS
LIQUID FLOW
LIQUID METAL COOLANT
LITHIUM FLUORIDES
MATERIALS TESTING
MEASURED VALUES
MELTING
METALLURGY
NICKEL ALLOYS
NICKEL FLUORIDES
NIOBIUM ALLOYS
PHYSICS
PLANNING
PLUTONIUM 239
PLUTONIUM FLUORIDES