Development of LMR physics technology in the United States
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7090469
- Dept. of Energy, Washington, DC (United States)
Reactor physics technology for liquid-metal reactor (LMR) applications has been developed through a wide range of research activities carried out by US National laboratory, industrial, and university organizations.These were focused on the design of the Experimental Breeder Reactor II (EBR-II), Fast Flux Test Facility (FFTF), Clinch River Breeder Reactor, large-scale prototype breeder, and more recently on the Integral Fast Reactor, and Power Reactor Inherently Safe Module modular reactor concepts. Significant advancements are noted in the accuracy and economics of computational methodology, the quality of the basic nuclear data used for LMR design, and the quality of integral measurements used to support design and licensing activities. Cooperative efforts among US organizations have been the key to many advances. The systematic application of covariance data files for both integral and differential data contributes to further improvements in LMR core design technology. Since advanced LMRs can potentially provide a major fraction of electric power over the next millenium, LMR technology development is worthy of the best efforts. The major goals are reasonable construction costs, a high degree of natural safety, good operational reliability, and an economical, environmentally attractive fuel cycle. The successful operations of FFTF and EBR-II and the progress in reactor physics in recent years are good indications one can meet the challenge of introducing advanced LMRs.
- OSTI ID:
- 7090469
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACTINIDES
ANL
AVAILABILITY
BREEDER REACTORS
CALCULATION METHODS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
CONSTRUCTION
DESIGN
EBR-2 REACTOR
EFFICIENCY
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
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FAST REACTORS
FBR TYPE REACTORS
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FLUID MECHANICS
FUEL CYCLE
FUEL ELEMENTS
FUEL MANAGEMENT
HEAT TRANSFER
HYDRAULICS
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
METALS
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NUCLEAR DATA COLLECTIONS
PHYSICS
POWER REACTORS
RARE EARTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTOR MATERIALS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
RELIABILITY
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
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TRANSMUTATION
TRANSURANIUM COMPOUNDS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
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210500* -- Power Reactors
Breeding
ACTINIDES
ANL
AVAILABILITY
BREEDER REACTORS
CALCULATION METHODS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
CONSTRUCTION
DESIGN
EBR-2 REACTOR
EFFICIENCY
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FLUID MECHANICS
FUEL CYCLE
FUEL ELEMENTS
FUEL MANAGEMENT
HEAT TRANSFER
HYDRAULICS
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
METALS
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NUCLEAR DATA COLLECTIONS
PHYSICS
POWER REACTORS
RARE EARTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTOR MATERIALS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
RELIABILITY
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
TRANSMUTATION
TRANSURANIUM COMPOUNDS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VALIDATION