SPERT I DESTRUCTIVE TEST PROGRAM SAFETY ANALYSIS REPORT

Technical Report · Fri Jun 15 04:00:00 EDT 1962

DOI:https://doi.org/10.2172/4775396· OSTI ID:4775396

Spano, A. H.; Miller, R. W.

The water-moderated core used for destructive experiments is mounted in the Spent I open-type reactor vessel, which has no provision for pressurization or forced coolant flow. The core is an array of highly enriched aluminum clad, plate-type fuel assemblies, using four bladetype, gang-operated control rods. Reactor transients are initiated at ambient temperature by step-insentions of reactivity, using a control rod which can be quickly ejected from the core. Following an initial series of static measurements to determine the basic- reactor properties of the test core, a series of nondestructive, self-limiting power excursion tests was performed, which covered a reactor period range down to the point where minor fuel plate damage first occurred -approximately for a 10- msec period test. These tests provided power, temperature, and pressure data. Additional kinetic teste in the period region between 10 and 5 msec were completed to explore the region of limited core damage. Fuel plate damage results included plate distortion, cladding cracking, and fuel melting. These exploratory tests were valuable in revealing unexpected changes in the dependence of pressure, temperature, burst energy, and burst shape parameters on reactor period, although the dependence of peak power on reactor period was not significantly changed. An evaluation of hazards involved in conducting the 2- msec test, based on pessimistic assumptions regarding fission product release and weather conditions, indicates that with the procedural controls normally exercised in the conduct of any transient test at Spent and the special controls to be in effect during the destructive test series, no significant hazard to personnel or to the general public will be obtained. All nuclear operation is conducted remotely approximately 1/2 mile from the reactor building. Discussion is also given of the supervision and control of personnel during and after each destructive test, and of the plans for re-entry, cleanup, and restoration of the facility. (auth)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-17-001010
• OSTI ID: 4775396
• Report Number(s): IDO-16790
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM
BURNOUT
CLEANING
CONTROL ELEMENTS
CRACKS
DECONTAMINATION
ENVIRONMENT
EXCURSIONS
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
LEAKS
LIQUID FLOW
MELTING
PERFORMANCE
PERSONNEL
PLATES
POWER
PRESSURE
QUANTITATIVE ANALYSIS
RADIATION PROTECTION
REACTIVITY
REACTOR KINETICS
REACTOR PERIOD
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
REMOTE CONTROL
RODS
SPERT-1
TEMPERATURE
TESTING
TRANSIENTS
URANIUM
WATER MODERATOR