QUARTERLY TECHNICAL REPORT, SPERT PROJECT, JULY, AUGUST, SEPTEMBER, 1960

Technical Report · Fri Jul 01 04:00:00 EDT 1960

DOI:https://doi.org/10.2172/4015296· OSTI ID:4015296

Schroeder, F ed

Spert 1. Preliminary tests were carried out on waterfilled capsules containing dummy fuel rods in the reactor; no void growth was detected in the capsule for reactor periods of 10 to 900 msec. The results of the first series of tests with fuel-bearing plates in the capsule are reported. Examination of the results of the large-amplitude, low-power oscillator test of June 1960 indicate that the describing-function phase results agree well with theory; however, a frequency-dependent deviation from theory is noted. Spert II. Critical experiments were made for close-packed and expanded D/sub 2/0-moderated cores. Spert III. The effects of coolant flow on the reactor response to reactivity changes were studied over the water velocity range of 0 to 18 ft/sec for initial asymptotic periods of 500 to 10 msec. The post-burst equilibrium power is proportional to the flow rate, and 18 ft/sec flow velccity eliminates the initial power peak for power excursions of period>100 msec. Engineerina. D/ sub 2/0 losses in Spert II are discussed. Burnout heat flux calculations were made for Spert III including the effects of two-phase flow. Hydraulic tests of Spert type-D fuel assembly channel flow distributions indicate that, for a Spert IV 20-assembly configuration, the maximum deviation from average channel flow is 14% for upflow and 6% for downflow. (D.L.C.)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-15-025591
• OSTI ID: 4015296
• Report Number(s): IDO-16677
• Country of Publication: United States
• Language: English

Related Subjects

BURNOUT
CONFIGURATION
COOLANT LOOPS
DISTRIBUTION
EQUATIONS
EXCURSIONS
FLUID FLOW
FREQUENCY
FUEL ELEMENTS
HEATING
HEAVY WATER MODERATOR
HYDRAULICS
IRRADIATION
LOSSES
MOCKUP
POWER
REACTIVITY
REACTOR OSCILLATORS
REACTOR TECHNOLOGY
RESEARCH REACTORS
SPERT-1
SPERT-3
TESTING
VARIATIONS
VELOCITY
WATER COOLANT
WATER MODERATOR