SODIUM GRAPHITE REACTOR. Quarterly Progress Report, July-September 1954

Technical Report · Wed Dec 01 00:00:00 EST 1954

DOI:https://doi.org/10.2172/4804990· OSTI ID:4804990

Siegel, S; Inman, G.M. eds.

Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up on Th--U/sup 235/ alloy. Calculations were made on neutron leakage through the SRE shield. Research on reactor fuel elements and reactor materials are described. Corrosion and irradiation damage data at 5 x 10/sup 7/ r dose (150 deg F) on toluene as the SRE shield coolant indicate that the radioinduced corrosion of Fe, Al, and Cu in the SRE shield should be negligible. Preliminary results are summarized for l-Mev electron ir radiation studies of terphenyls at 400 to 450 deg C. Sodium Reactor Experiment. Progress is reported for various portions of the SRE project: reactor design and evaluation, fuel elements, moderator, reflector, structure, reactor cooling and heat transfer, instrumentation and control, shielding, and reactor services. (D.L.C.)

• Research Organization: North American Aviation, Inc., Downey, CA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AT-11-1-GEN-8
• NSA Number: NSA-16-009657
• OSTI ID: 4804990
• Report Number(s): NAA-SR-1109
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ADSORPTION
ALUMINUM
BREEDING
CONFIGURATION
CONTROL
CONTROL SYSTEMS
COOLANT LOOPS
COOLANTS
COOLING
COPPER
CORROSION
DISTRIBUTION
ECONOMICS
EFFICIENCY
ELECTRON BEAMS
EQUATIONS
FAILURES
FERTILE MATERIALS
FISSIONABLE MATERIALS
FUEL ELEMENTS
GRAPHITE MODERATOR
HEAT TRANSFER
HIGH TEMPERATURE
IMPURITIES
INSTRUMENTS
IRON
IRRADIATION
LIQUID METAL COOLANT
LOSSES
MAINTENANCE
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
MODERATORS
MONITORING
NEUTRON FLUX
NEUTRONS
NUMERICALS
PLANNING
PLUTONIUM
POLYPHENYLS
POWER
POWER PLANTS
PRODUCTION
RADIATION DOSES
RADIATION EFFECTS
REACTIVITY
REACTOR CORE
REACT