THE SODIUM-GRAPHITE REACTOR. PART II

Journal Article · Mon Oct 01 04:00:00 EDT 1962 · Nuclear Eng.

OSTI ID:4768774

Wensch, G W

S>A general program of reactor and sodium system developmrnt id being conducted for USAEC in order to develop sodium-graphite reactor (SGR) technology to the point where plants of 300 and 1000 Mw(e) can be built. Experimental facilities for testing SGR components and for safety studies are described. Plant characteristics and operating data are tabulated for the Hallam piant, and its economics and fuel cycle costs are discussed in detail. The technical potential of the SGR is discussed, and costs and operating data are tabulated for the projected 300- and 1000-Mw(e) plants (D.L.C.)

• Research Organization: U.S. Atomic Energy Commission, Washington, D.C.
• NSA Number: NSA-17-002594
• OSTI ID: 4768774
• Journal Information: Nuclear Eng., Journal Name: Nuclear Eng. Vol. Vol: 7
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BREEDING
BURNUP
COOLANTS
ECONOMICS
FUEL CYCLE
GRAPHITE MODERATOR
HNPF
LABORATORY EQUIPMENT
OPERATION
PLANNING
POWER PLANTS
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
REPROCESSING
SGR
SODIUM
TABLES
TESTING