QUARTERLY TECHNICAL REPORT ON SPERT PROJECT, JULY, AUGUST, SEPTEMBER 1961

Technical Report · Fri Dec 15 04:00:00 EST 1961

OSTI ID:4812810

Schroeder, F ed

The kinetic behavior of a 4%-enriched UO/sub 2/-pin-fueled water- moderated core in Spert I is investigated. Both step and ramp transients are applied, and the pins may be either free to bow or constrained to remain straight. Power excursion tests are performed in Spert II, in order to investigate the response of a D/sub 2/O-moderated core to step reactivity insertions at room temperature and at initial system pressures of 15 to 375 psig. The effects of initial system temperature and subcooling on the system response to step reactivity insertions are studied in Spert III. In addition, the hydraulic characteristics of the fuel plate assembly used in Spert II are examined. (T.F.H.)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-16-009652
• OSTI ID: 4812810
• Report Number(s): IDO-16726
• Country of Publication: United States
• Language: English

Related Subjects

CONFIGURATION
COOLANT LOOPS
DEFORMATION
EXCURSIONS
EXPANSION
FLUID FLOW
FUEL ELEMENTS
HEAT TRANSFER
HEAVY WATER MODERATOR
HIGH TEMPERATURE
HYDRAULICS
LOW TEMPERATURE
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
NEUTRON FLUX
PLATES
POWER PLANTS
PRESSURE
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
RODS
SPERT-1
SPERT-2
STABILITY
TEMPERATURE
TENSILE PROPERTIES
TRANSFER FUNCTIONS
TRANSIENTS
URANIUM DIOXIDE
VARIATIONS
WATER MODERATOR