Process inherent, ultimately safe BWR
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5547125
A new type of boiling water reactor (BWR) with passive safety systems has been conceived - the process inherent, ultimately safe (PIUS) BWR. The reactor core and non-nuclear portion of the plant are similar to current BWR designs, but a special, prestressed concrete reactor vessel (PCRV) with unique internal design replaces most of the nuclear island. A natural circulation PIUS BWR with key components inside the PCRV is described. Forced circulation is an option. The reactor pressure, temperature, and thermal efficiencies match current BWRs.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 5547125
- Report Number(s):
- CONF-851115-; TRN: 86-020531
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 50; Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 10 Nov 1985
- Country of Publication:
- United States
- Language:
- English
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Journal Article
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Sat Feb 01 00:00:00 EST 1986
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OSTI ID:5547125
Process-inherent, ultimate-safety (PIUS) boiling-water reactor
Conference
·
Tue Jan 01 00:00:00 EST 1985
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OSTI ID:5547125
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Thesis/Dissertation
·
Wed Jan 01 00:00:00 EST 1992
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OSTI ID:5547125
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ECCS
REACTOR SAFETY
AFTER-HEAT REMOVAL
BORON
CAPITALIZED COST
DESIGN
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTIVITY
REACTOR CORES
SAFETY ENGINEERING
BUILDING MATERIALS
CONCRETES
CONTAINERS
COST
ELEMENTS
ENGINEERED SAFETY SYSTEMS
ENGINEERING
MATERIALS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
REMOVAL
SAFETY
SEMIMETALS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ECCS
REACTOR SAFETY
AFTER-HEAT REMOVAL
BORON
CAPITALIZED COST
DESIGN
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTIVITY
REACTOR CORES
SAFETY ENGINEERING
BUILDING MATERIALS
CONCRETES
CONTAINERS
COST
ELEMENTS
ENGINEERED SAFETY SYSTEMS
ENGINEERING
MATERIALS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
REMOVAL
SAFETY
SEMIMETALS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled