Improving the conceptual design of the Ohio State University Inherently Safe Reactor
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7231653
- Ohio State Univ., Columbus (United States)
The Ohio State University Inherently Safe Reactor (OSU-ISR) is a conceptual design for a 340-MW(electric) (1,000-MW(thermal)) natural circulation, indirect cycle, small boiling water reactor. The design features a multi-cavity prestressed concrete reactor vessel (PCRV) that contains all primary loop components. Because of the water level change under normal operation due to level swell originating from voiding in the core and also possible level changes during accident conditions, the location and the size of the water bypass orifice and the initial water level (i.e., cold shutdown) are very important OSU-ISR design parameters. If the water level falls below the water bypass orifice, natural circulation cannot be maintained. If the water level rises above the steam separators, then the C/E performance will be impaired. This paper presents a parametric analysis of the water swell due to voiding and discuss the impact of this analysis on the OSU-ISR design.
- OSTI ID:
- 7231653
- Report Number(s):
- CONF-920606--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
- Country of Publication:
- United States
- Language:
- English
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·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
Boiling Water Cooled
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AFTER-HEAT REMOVAL
BOILERS
BWR TYPE REACTORS
COMPUTER CODES
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ENRICHED URANIUM REACTORS
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MASS TRANSFER
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PARAMETRIC ANALYSIS
POWER REACTORS
PRESSURE SUPPRESSION
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PRIMARY COOLANT CIRCUITS
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REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
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SECONDARY COOLANT CIRCUITS
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Nonbreeding
Light-Water Moderated
Boiling Water Cooled
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AFTER-HEAT REMOVAL
BOILERS
BWR TYPE REACTORS
COMPUTER CODES
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CONDENSERS
CONTAINERS
CONVECTION
COOLING SYSTEMS
D CODES
DESIGN
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
HEAT TRANSFER
KINETICS
LEVELS
MASS TRANSFER
NATURAL CONVECTION
PARAMETRIC ANALYSIS
POWER REACTORS
PRESSURE SUPPRESSION
PRESSURE VESSELS
PRESSURIZERS
PRIMARY COOLANT CIRCUITS
R CODES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
SECONDARY COOLANT CIRCUITS
SIMULATION
SPECIFICATIONS
STEAM GENERATORS
THERMAL REACTORS
VAPOR CONDENSERS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS