SPERT IV FACILITY
The Special Power Excursion Reactor Test IV (Spert IV) reactor is a swimming-pool type nuclear research reactor which was constructed to provide a facility for conducting reactor kinetic behavior and safety investigations especially in the field of reactor stability. The facility was designed to incorporate a wide range of flexibility in flow rates and direction of flow, and has a heat removal capacity of 1 Mw thermal in addition to the heal sink capacity of the reactor pools. The engineering features of the reactor and support ing 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-16-014339
- OSTI ID:
- 4785456
- Report Number(s):
- IDO-16745
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CONFIGURATION
COOLANT LOOPS
EXCURSIONS
FLUID FLOW
HEAT TRANSFER
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
NEUTRON FLUX
PLANNING
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SPERT-1D
SPERT-4
STABILITY
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS
VARIATIONS
WATER COOLANT
WATER MODERATOR
COOLANT LOOPS
EXCURSIONS
FLUID FLOW
HEAT TRANSFER
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
NEUTRON FLUX
PLANNING
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SPERT-1D
SPERT-4
STABILITY
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS
VARIATIONS
WATER COOLANT
WATER MODERATOR