QUARTERLY PROGRESS REPORT FOR THE PERIOD JULY 1 TO SEPTEMBER 30, 1958

Technical Report · Sat Oct 31 04:00:00 EST 1959

DOI:https://doi.org/10.2172/4289488· OSTI ID:4289488

Garbe, R. W.; Walchli, H. E.

An evaluation and the resulting conclusions of work performed are given for each project in which definitive progress was made. The principle progress consisted of: obtaining promising fuel fabrication results from production scale investigations of simplified UO/sub 2/ preparations methods, presintering operation elimination, increasing pellet densities and reductions of UO/sub 2/ losses; successfully brazing a ninety-five inch long experimental fuel subassembly in which all joints, including outside ferrules and control rod rubbing strips, had brazed fillets; completing the fabrication of the last group of MTR process water irradiation samples and all of the in-pile test loop samples except for the specimens containing 27% enriched pellets; performing a nuclear analysis of various fuel assembly designs as part of an over-all evaluation of fuel assembly bowing in the Yankee reactor; completing corrosion studies of primary plant materials in static autoclaves to aid in the selection of a pH control agent; developing a Compromise Design'' for the fueh assembly which incorporates a series of small design changes to eliminate the possibility of restricting control rod motion by interference due to a superposition of bowing of the fuel assembly and an adverse accummulation of mechanical tolerances; completing the calculation of the moderator temperature coefficient, the Doppler temperature coefficient, the void coefficient, neutron lifetime, and delayed neutron fraction; obtaining flux profiles, flux peaking, flux spectrum, peripheral fuel rod worth, void coefficient, temperature coefficient, and control rod worth data from the Critical Reactor Experiments with a 3: 1 water-to-uranium metal ratio core at the Westinghouse Reactor Evaluation Center; continuing instrumentation and individual component operational testing of the in-pile test loop; and analyzing the results of the post-irradiation examination of the second group of process water samples and delivery of the last group of samples to the MTR. (For preceding period see YAEC-87.) (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-13-009482
• OSTI ID: 4289488
• Report Number(s): YAEC-97
• Country of Publication: United States
• Language: English

Related Subjects

ACIDITY
BRAZING
CANNING
CONFIGURATION
CONTROL ELEMENTS
COOLANT LOOPS
CORROSION
CORROSION PROTECTION
DEFORMATION
DENSITY
EFFICIENCY
ENRICHMENT
EQUATIONS
EXPANSION
FABRICATION
FAILURES
FUEL ELEMENTS
HIGH TEMPERATURE
IMPURITIES
IN PILE LOOPS
IRRADIATION
JOINTS
LIFETIME
LOSSES
MATERIALS TESTING
MECHANICAL STRUCTURES
MOCKUP
MODERATORS
MONITORING
NEUTRON FLUX
NEUTRONS
PELLETS
PLANNING
POWER PLANTS
PRODUCTION
REACTIVITY
REACTOR CORE
REACTORS
REPROCESSING
RODS
SAMPLING
SINTERING
SPECTRAL SHIFT
TEMPERATURE
THERMAL STRESSES
URANIUM DIOXIDE
WATER COOLANT