MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING, SEPTEMBER 30, 1960
The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit use of gases other than helium. It was further directed that the reactor should be designated BORE for Beryllium- Oxide Reactor Experiment. Reactor development work was mainly in connection with the BORE preliminary design. It was established that the most important information which could be provided by a 10 Mw(t) reactor experiment would be on performance of fuel elements and moderator bodies. This required that the experirment duplicate the power density in the fuel and moderator that would exist in the full size reactor and made it advisable to use full length fuel elements. This resulted in an unconventionally shaped core which is roughly cylindrical with the length more than twice its mean diameter. Studies continued on performance of fuel elements, and methods were developed for calculation of thermal stress in BeO-moderated modules. These studies are equally applicable to the MGCR prototype and BORE. A thermal analysis of the MGCR pressure vessel and thermal shields was performed and means of externally cooling the vessel were studied. Some of the components of the experimental control rod drive mechanism were received. Endurance tests of a ball-nut lead screw in hot helium continued. Heat exchanger tests were resumed after an interruption due to leaks in the tube to tubesheet joints in the test unit. Plant control studies were continued with analyses of the system dynamics with a turbomachinery configuration in which the high pressure turbine provides the output power. This arrangement was found to be more sensitive than the low-pressure drive system. Turbomachinery component tests are providing stage performance data. The seal and bearing test rig was completed and tests were begun. Physics calculations were made for the BORE design. Basic physics information on Fermi age and neutron thermalization in BeO was provided during the quarter by experlments in the linear accelerator. Materials work continued with further investigations of the effect of additives on properties of UC/sub 2/--BeO diluted fuel bodies. Hot cell examination of the MTR-31-3 fuel capsule indicated no significant dimensional changes after burnups from 30,000 to 45,000 Mwd/T. An experiment to determine irradiation effects on BeO was inserted in GETR during September. Work was started on development of high density BeO bodies. Structural materials research continued with completion of a second series of self-welding tests of different metal pairs in high temperature helium. A series of galling tests and a series of creep rupture tests of weld specimens in SA302-B steel were completed. Work on site development included establishing requirements of the BORE for buildings, auxiliary facilities, and utilities. (auth)
- Research Organization:
- General Atomics, San Diego, CA (United States); General Dynamics Corp. Electric Boat Div., Groton, Conn.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(04-3)-187
- NSA Number:
- NSA-16-006213
- OSTI ID:
- 4804305
- Report Number(s):
- GA-1738
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
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MARITIME GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING SEPTEMBER 30, 1959
MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for Period Ending June 30, 1960
Related Subjects
ACCELERATORS
BEARINGS
BERYLLIUM MODERATOR
BERYLLIUM OXIDES
BUILDINGS
BURNUP
CONFIGURATION
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
COOLING
CREEP
CRITICALITY
CROSS SECTIONS
CYLINDERS
DEFORMATION
DENSITY
DIFFUSION LENGTH
EBOR
ECONOMICS
ENVIRONMENT
EQUATIONS
FAILURES
FAST NEUTRONS
FERMI AGE
FUEL CANS
FUEL ELEMENTS
GAS COOLANT
GETR
HEAT EXCHANGERS
HEAT TRANSFER
HELIUM
HIGH TEMPERATURE
HOT CELLS
IMPURITIES
INERT GASES
IRRADIATION
JOINTS
LEAD
LEAKS
MACHINE PARTS
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
METALS
MGCR
MODERATORS
MOTORS
NEUTRON FLUX
NUMERICALS