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Title: Safety Aspects of the IFR Pyroprocess Fuel Cycle

Conference ·
OSTI ID:5497065

This paper addresses the important safety considerations related to the unique Integral Fast Reactor (IFR) fuel cycle technology, the pyroprocess. Argonne has been developing the IFR since 1984. It is a liquid metal cooled reactor, with a unique metal alloy fuel, and it utilizes a radically new fuel cycle. An existing facility, the Hot Fuel Examination Facility-South (HFEF/S) is being modified and equipped to provide a complete demonstration of the fuel cycle. This paper will concentrate on safety aspects of the future HFEF/S operation, slated to begin late next year. HFEF/S is part of Argonne's complex of reactor test facilities located on the Idaho National Engineering Laboratory. HFEF/S was originally put into operation in 1964 as the EBR-II Fuel Cycle Facility (FCF) (Stevenson, 1987). From 1964-69 FCF operated to demonstrate an earlier and incomplete form of today's pyroprocess, recycling some 400 fuel assemblies back to EBR-II. The FCF mission was then changed to one of an irradiated fuels and materials examination facility, hence the name changes to HFEF/S. The modifications consist of activities to bring the facility into conformance with today's much more stringent safety standards, and, of course, providing the new process equipment. The pyroprocess and the modifications themselves are described more fully elsewhere (Lineberry, 1987; Chang, 1987).

Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
5497065
Report Number(s):
CONF-890841-4; ON: DE90002177; TRN: 89-030978
Resource Relation:
Conference: International Workshop on Safety of Nuclear Installations of the Next Generation and Beyond, Chicago, IL (United States), 28-31 Aug 1989
Country of Publication:
United States
Language:
English

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Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
EBR-2 REACTOR
FUEL REPROCESSING PLANTS
ACCIDENTS
AIR FILTERS
ARGON
COMBUSTION
COMPLIANCE
CONTAINERS
COOLING SYSTEMS
CRITICALITY
DESIGN
DIFFUSION
EARTHQUAKES
EMERGENCY PLANS
EQUIPMENT
EXHAUST SYSTEMS
FIRE PREVENTION
FISSION PRODUCTS
FLOW RATE
FUEL CYCLE
HOT CELLS
IFR REACTOR
MATERIALS HANDLING
MELTDOWN
MITIGATION
PARTICULATES
RADIATION PROTECTION
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
REACTOR SAFETY
REGULATIONS
REGULATORY GUIDES
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
TRANSIENTS
BREEDER REACTORS
CASKS
CHEMICAL REACTIONS
DOCUMENT TYPES
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FILTERS
FLUIDS
FUEL ELEMENTS
GASES
ISOTOPES
LABORATORY EQUIPMENT
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
MATERIALS
NONMETALS
NUCLEAR FACILITIES
OXIDATION
PARTICLES
POLLUTION CONTROL EQUIPMENT
POWER REACTORS
RADIOACTIVE MATERIALS
RARE GASES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SEISMIC EVENTS
SODIUM COOLED REACTORS
THERMOCHEMICAL PROCESSES
WASTE DISPOSAL
WASTE MANAGEMENT
ZERO POWER REACTORS
Nuclear Criticality Safety Program (NCSP)
Integral Fast Reactor (IFR)
Fuel Cycle Technology
Hot Fuel Examination Facility-South (HFEF/S)
EBR-II Fuel Cycle Facility (FCF)
Fuel Rods
Fuel Assembly Hardware
Safety Exhaust System (SES)
Fission Gas Release
Cell Atmosphere
Metal Fire
Argon Cell
Wastecan Spill
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
055001 - Nuclear Fuels- Safeguards
Inspection
& Accountability- Technical Aspects
050800 - Nuclear Fuels- Spent Fuels Reprocessing