Integral fast reactor concept inherent safety features
Conference
·
OSTI ID:5687032
The Integral Fast Reactor (IFR) is an innovative liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFT development effort are improved economics and enhanced safety. The design features that together fulfill these goals are: 1) a liquid metal (sodium) coolant, 2) a pool-type reactor primary system configuration, 3) an advanced ternary alloy metallic fuel, and 4) an integral fuel cycle. This paper reviews the design features that contribute to the safety margins inherent to the IFR concept. Special emphasis is placed on the ability of the IFR design to accommodate anticipated transients without scram (ATWS).
- OSTI ID:
- 5687032
- Report Number(s):
- CONF-861211-
- Resource Relation:
- Conference: American Society of Mechanical Engineers winter meeting, Anaheim, CA, USA, 7 Dec 1986; Other Information: Technical Paper 86-WA/NE-14
- Country of Publication:
- United States
- Language:
- English
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·
OSTI ID:5687032
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
SODIUM COOLED REACTORS
DESIGN
PLANNING
REACTOR SAFETY
ANL
ATWS
COST BENEFIT ANALYSIS
FAST REACTORS
FUEL CYCLE
LIQUID METALS
PRIMARY COOLANT CIRCUITS
REVIEWS
SCRAM
SODIUM
TERNARY ALLOY SYSTEMS
TRANSIENTS
ACCIDENTS
ALKALI METALS
ALLOY SYSTEMS
COOLING SYSTEMS
DOCUMENT TYPES
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FLUIDS
LIQUID METAL COOLED REACTORS
LIQUIDS
METALS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWNS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
SODIUM COOLED REACTORS
DESIGN
PLANNING
REACTOR SAFETY
ANL
ATWS
COST BENEFIT ANALYSIS
FAST REACTORS
FUEL CYCLE
LIQUID METALS
PRIMARY COOLANT CIRCUITS
REVIEWS
SCRAM
SODIUM
TERNARY ALLOY SYSTEMS
TRANSIENTS
ACCIDENTS
ALKALI METALS
ALLOY SYSTEMS
COOLING SYSTEMS
DOCUMENT TYPES
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FLUIDS
LIQUID METAL COOLED REACTORS
LIQUIDS
METALS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWNS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding