THE SODIUM GRAPHITE REACTOR POWER PLANT FOR CPPD

Technical Report · Fri Oct 31 04:00:00 EST 1958

DOI:https://doi.org/10.2172/4315587· OSTI ID:4315587

Olson, R L; Gerber, R C; Gordon, R B; Ross-Clunis, H A; Stolz, J F

The plant arrangement, component design, and the functions of various systems are described and illustrated. Relative estimated costs of the systems and major components are indicated. The reactor core is designed around requiremouts for 254 thermal megawatts, 950 deg F maximum sodium temperature, stainless steel clad graphite moderator blocks, and low enrichment (0.015 to 0.04 U/sup 235/) uranium fuel elements. The fuel cycle is described for the possible fuel elements. The fuel cost factors are discussed. Burn-up limitations encountered for metallic fuel in the SGR temperature range indicate UO/sub 2/ the more desirable choice. The estimated cost of electrical energy associated with the UO/sub 2/ fuel is given. (auth)

• Research Organization: Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
• Sponsoring Organization: USDOE
• NSA Number: NSA-12-015028
• OSTI ID: 4315587
• Report Number(s): A/CONF.15/P/608
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
CANNING
CONFERENCE
CONFIGURATION
COOLANT LOOPS
ECONOMICS
EFFICIENCY
ELECTRICITY
ENRICHMENT
FUEL ELEMENTS
GRAPHITE MODERATOR
HIGH TEMPERATURE
HNPF
LIQUID METAL COOLANT
MEASURED VALUES
MECHANICAL STRUCTURES
METALS
MODERATORS
PHYSICS
PLANNING
POWER PLANTS
REACTOR CORE
REACTOR FUELING
REACTORS
SGR
SODIUM
TEMPERATURE
URANIUM 235
URANIUM DIOXIDE
ZONES