Maritime Gas-Cooled Reactor Program (Quarterly Progress Report, 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 within 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 experiment 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 experiments in the linear accelerator.
- Research Organization:
- General Dynamics Corp., San Diego, CA (United States); Electric Boat Div., Groton, CT (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC); Maritime Administration; USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- NSA Number:
- NSA-16-006213
- OSTI ID:
- 4804305
- Report Number(s):
- GA--1738; TID--4500
- Country of Publication:
- United States
- Language:
- English
Similar Records
MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for the Period Ending June 30, 1961
NUCLEAR SAFETY CONSIDERATIONS AFFECTING THE DESIGN OF THE MARITIME GAS COOLED REACTOR
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
Fluid systems
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
Nuclear Criticality Safety Program (NCSP)
Reactor experiment