MARITIME GAS-COOLED REACTOR PROGRAM. Quarterly Progress Report for the Period Ending June 30, 1961

Technical Report · Thu Oct 31 00:00:00 EST 1963

OSTI ID:4645887

Reactor Development. Thermal stress tests were carried out on square- annular BeO blocks, and preliminary results are given. Design and thermal analysis were carried out on the EBOR core, control element, and cooling systems. The thermal emissivity coefficient of Hastelloy X cladding was measured at surface temperatures of 1300 to 1700 deg F. Development of control rod drive mechanisms is continuing. A wet-or-dry refueling system is being developed for EBOR. Rotating Machinery. The modification of the 1300 deg F design of MGCR turbomachinery for 1500 deg F operation is described. Tests of the diffuser, exhaust hoods compressors, etc. are discussed. Reactor Physics. Measurements are reported of experiments on the EBOR critical assembly, and a comparison of calculated and experimental perturbations is made. The effects of water flooding on the EBOR core reactivity were studied. Heating rates were estimated in the control rods and moderator. A comparison is made of the LASL and General Atomic data for the U as fission resonance integral over several energy ranges. The calculated capture-to-fission ratios alpha were also compared with experiment. Materials Development. The compressive strength and oxidation resistance of BeO- UO/sub 2/ fuel specimens were studied as functions of grain size. Some preliminary results are reported of the irradiation program. Radiation effects on the axial crushing strength of BeO--UO/sub 2/ pellets are tabulated. Results of BeO irradiations are also given. Creep and stress rupture tests were carried out on Hastelloy X at 1600 deg F in different atmospheres. The fabrication development of fuel elements and control rods for MGCR is described. Stress- rupture data are reported for several alloys. (D.L.C.)

• Research Organization: General Atomic Div. General Dynamics Corp., San Diego, Calif.; General Dynamics Corp. Electric Boat Div., Groton, Conn.
• DOE Contract Number: AT(04-3)-187
• NSA Number: NSA-17-038431
• OSTI ID: 4645887
• Report Number(s): GA-2372
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-63
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ALLOYS
BERYLLIUM OXIDES
CAPTURE
CHROMIUM ALLOYS
COMPRESSORS
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
CRACKS
CREEP
CRITICAL ASSEMBLIES
EBOR
FABRICATION
FISSION
FUEL CANS
FUEL ELEMENTS
GAS COOLANT
GRAIN SIZE
HASTELLOY
HEATING
HIGH TEMPERATURE
IRRADIATION
MATERIALS TESTING
MEASURED VALUES
MGCR
MODERATORS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OPERATION
OXIDATION
PELLETS
PLANNING
PUMPS
RADIATION EFFECTS
REACTIVITY
REACTOR CORE
REACTOR FUELING
REACTORS
RESONANCE NEUTRONS
SHIPS
STRESSES
TABLES
TESTING
THERMAL STRESSES
TURBINES
URANIUM 235
URANIUM DIOXIDE
WATER