THE EXPERIMENTAL BERYLLIUM OXIDE REACTOR. MARITIME GAS-COOLED REACTOR PROGRAM

Technical Report · Sat Jul 01 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/4826933· OSTI ID:4826933

Moore, W C

LIUM OXIDE REACTOR. MARITIME GAS-COOLED The Experimental Beryllium Oxide Reactor, EBOR, will be constructed at the National Reactor Testing Station as the AEC portion of the joint Maritime Administration--AEC Maritime Gas Cooled Reactor Program. The ultimate goal of the Program is the development of nuclear power plants employing a helium cooled and beryllium oxide moderated reactor directly coupled to a closed cycle gas turbine. The objective is to obtain compact nuclear engines suitable for use either in a merchant ship propulsion system or an intermediate size central station power plant in the 20 to 100 Mw(e) size range. The EBOR is a l0 Mw(t) test of the basic fuel element and moderator designs. It is capable of being up-graded in power at a later date to a test of the nuclear reactor turbine concept. The objective of the experiment is outlined. The principal reactor components to be tested and the test facility are described. (auth)

• Research Organization: General Atomic Div. General Dynamics Corp., San Diego, Calif.
• NSA Number: NSA-16-003818
• OSTI ID: 4826933
• Report Number(s): GA-2385
• Country of Publication: United States
• Language: English

Related Subjects

BERYLLIUM MODERATOR
BERYLLIUM OXIDES
COOLANT LOOPS
EBOR
ELECTRICITY
FABRICATION
FUEL ELEMENTS
GAS COOLANT
GASES
HELIUM
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
MODERATORS
PLANNING
POWER PLANTS
PRODUCTION
PROPULSION
REACTOR CORE
REACTOR TECHNOLOGY
SHIPS
TESTING
TURBINES