SPERT III REACTOR FACILITY
The Special Power Excursion Reactor Test III (Spert III) reactor is a pressurized-water nuclear-research reactor which was constructed to provide a facility for conducting reactor kinetic behavior and safety investigations. The investigations are designed to provide information for the advancement of pressurized-water and boiling-water reactor technology and safety. The facility was designed for operations up to pressures of 2500 psig and temperatures of 670 deg F and incorporates essential features typical of pressurized-water and boiling-water reactors. The engineering features of the reactor and supporting process equipment as constructed at the National Reactor Testing Station are described. (auth)
- Research Organization:
- Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
- DOE Contract Number:
- AT(10-1)-205
- NSA Number:
- NSA-16-003830
- OSTI ID:
- 4826907
- Report Number(s):
- IDO-16721
- Country of Publication:
- United States
- Language:
- English
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BOILING
CONFIGURATION
CONTROL SYSTEMS
EFFICIENCY
EXCURSIONS
FABRICATION
HEAT TRANSFER
HIGH TEMPERATURE
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
NEUTRON FLUX
PLANNING
PRESSURE
REACTIVITY
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SPERT-3
STABILITY
TEMPERATURE
TESTING
TRANSIENTS
VARIATIONS
WATER COOLANT
CONFIGURATION
CONTROL SYSTEMS
EFFICIENCY
EXCURSIONS
FABRICATION
HEAT TRANSFER
HIGH TEMPERATURE
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
NEUTRON FLUX
PLANNING
PRESSURE
REACTIVITY
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SPERT-3
STABILITY
TEMPERATURE
TESTING
TRANSIENTS
VARIATIONS
WATER COOLANT