Direct reactor auxiliary cooling system for the 1000-MWE LMFBR developmental plant
Journal Article
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:5686017
The 1000-MWe LMFBR developmental plant design was prepared during 1978-1981. This paper provides a description and discusses the safety-related features of the direct reactor auxiliary cooling system proposed for the developmental plant. 2 refs.
- Research Organization:
- Rockwell Int, Canoga Park, Calif
- OSTI ID:
- 5686017
- Journal Information:
- Am. Soc. Mech. Eng., (Pap.); (United States), Vol. 81-JPGC-NE-7
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ENGINEERED SAFETY SYSTEMS
LMFBR TYPE REACTORS
REACTOR COOLING SYSTEMS
NUCLEAR POWER PLANTS
POWER RANGE 100-1000 MW
REACTOR SAFETY
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR COMPONENTS
REACTORS
SAFETY
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ENGINEERED SAFETY SYSTEMS
LMFBR TYPE REACTORS
REACTOR COOLING SYSTEMS
NUCLEAR POWER PLANTS
POWER RANGE 100-1000 MW
REACTOR SAFETY
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR COMPONENTS
REACTORS
SAFETY
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding