MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING DECEMBER 31, 1958

Technical Report · Mon Oct 31 04:00:00 EST 1960

OSTI ID:4182424

The MGCR program objectives are to develop and construct a land based prototype of a high-temperature nuclear reactor, coupled with a closed-cycle, gas- turbine system for maritime application. The first broad task undertaken by the MGCR program was a detailed study and evaluation of the various coolants and moderators which could be considered as realistic possibilities for this application.The evaluation program led to the selection of a graphite moderator and helium coolant as being the most feasible and having the greatest possibilities of leading to a reliable high performance power system. Development work is proceeding rapidly in the areas of materials development, reactor design, turbomachinery, and design and development of plant fluid and electrical systems and other components thereof. Two fuel element concepts under development are (1) a heterogeneous, rod-bundle element consisting of UO/sub 2/ bodies dispersed through an oxide diluent and encased in metal capsules and (2) a semihomogeneous fuel-moderator element consisting of metal-clad cylindrical fuel bodies inserted in graphite plates. Studies of the compatibility of metals with graphite in the temperature range 1500 to 1700 deg F were made. Nuclear analysis refined the estimates of nuclear performance given previously. Particular emphasis was placed on the control requirements, control-rod worth, and neutron thermalization in graphite. Design analysis of the concentric-duct piping led to the design of experiments on model ducts. Considerations of critical-speed and bearing problems of the turbomachinery and over-all cycle efficiency led to the conclusion that the MGCR plant cycle must definitely have intercooling to meet the desired performance. (See also GA-570.) (W.D.M.)

• Research Organization: General Atomic Div., General Dynamics Corp., San Diego, Calif.
• NSA Number: NSA-14-011294
• OSTI ID: 4182424
• Report Number(s): GA-744
• Country of Publication: United States
• Language: English

Related Subjects

CONTROL
COOLANTS
FUEL ELEMENTS
GAS COOLANT
GRAPHITE MODERATOR
HELIUM
HIGH TEMPERATURE
MGCR
MODERATORS
PERFORMANCE
PIPES
PLANNING
POWER PLANTS
REACTOR TECHNOLOGY
REACTORS
SHIPS
URANIUM OXIDES