SPERT PROJECT QUARTERLY TECHNICAL REPORT, APRIL-JUNE 1962

Technical Report · Fri Sep 21 00:00:00 EDT 1962

DOI:https://doi.org/10.2172/4759250· OSTI ID:4759250

Schroeder, F. ed.

Static measurements of various nuclear core parameters were completed for the highly enriched plate-type Al-clad core to be used for the Spert I integral core destructive test program. Self-limiting power excursion tests were performed with initial asymptotic reactor periods in the range of 934 to 4.6 msec to establish the transient response of the core and to obtain data for extrapolation to shorter-period tests in which violent destructive effects are expected. For tests with periods shorter than about 7 msec, fuel plate deformations were produced as a result of thermal stresses in the plates. Melting of fuel plates was obtained in two tests with periods of 5 and 4.6 msec. For tests with periods in the range of 9 to 4.6 msec, power burst shape changes were observed which result in an increase in the ratio of the energy release in the total burst to that at the time of the power peak, as the period is shortened. Maximum transient pressures never exceeded 10 psi for tests thus far performed. A series of self-limiting power excursion tests was initiated in Spert II to determine the effects of the initial system temperature on the kinetic response of the D/sub 2/Omoderated expanded core loading. The data indicate that as the initial system temperature is increased to near the saturation temperature, boiling becomes a more predominant shutdown mechanism with a consequent reduction in the peak power, burst energy, and fuel-plate surfacetemperature rise. The increased dependence on steam formation for shutdown as subcooling is decreased leads to relatively larger amplitudes for power oscillations following the initial burst. The larger unstable void volumes which are produced is the apparent reason for this occurrence. (auth)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-17-002617
• OSTI ID: 4759250
• Report Number(s): IDO-16806
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-63
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ALUMINUM
BOILING
DEFORMATION
ENERGY
ENRICHMENT
EXCURSIONS
FUEL CANS
FUEL ELEMENTS
HEAVY WATER MODERATOR
LOSSES
MEASURED VALUES
MELTING
OSCILLATIONS
PLATES
PRESSURE
PRODUCTION
QUANTITATIVE ANALYSIS
REACTIVITY
REACTOR CORE
REACTOR KINETICS
REACTOR PERIOD
REACTOR SAFETY
RESEARCH REACTORS
SHUTDOWN
SPERT-1
SPERT-2
STEAM
SURFACES
TEMPERATURE
TESTING
THERMAL STRESSES
TRANSIENTS
ZONES