Criticality Experiments with Fast Flux Test Facility Fuel Pins

Conference · Sun Nov 11 00:00:00 EST 1990

OSTI ID:6157966

Bierman, S. R. ^[1]

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1. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

A United States Department of Energy program was initiated during the early seventies at the Hanford Critical Mass Laboratory to obtain experimental criticality data in support of the Liquid Metal Fast Breeder Reactor Program. The criticality experiments program was to provide basic physics data for clean well defined conditions expected to be encountered in the handling of plutonium-uranium fuel mixtures outside reactors. One task of this criticality experiments program was concerned with obtaining data on PuO₂-UO₂ fuel rods containing 20--30 wt % plutonium. To obtain this data a series of experiments were performed over a period of about twelve years. The experimental data obtained during this time are summarized and the associated experimental assemblies are described.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6157966
• Report Number(s): PNL-SA-18405; CONF-901101-69; ON: DE91005050; TRN: 91-001724
• Resource Relation: Conference: American Nuclear Society Winter Meeting , Washington, DC (United States), 11-15 Nov 1990
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
LMFBR TYPE REACTORS
CRITICALITY
FUEL PINS
EXPERIMENTAL DATA
FFTF REACTOR
FUEL RODS
HYDROXIDE MODERATORS
MIXED OXIDE FUELS
NITRATES
ORGANIC MODERATORS
PLUTONIUM
URANIUM
ACTINIDES
BREEDER REACTORS
DATA
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUELS
INFORMATION
LIQUID METAL COOLED REACTORS
METALS
MODERATORS
NITROGEN COMPOUNDS
NUMERICAL DATA
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
TEST REACTORS
TRANSURANIUM ELEMENTS
Nuclear Criticality Safety Program (NCSP)
Experiments Program
Experimental Data
Experimental Assemblies
210500* - Power Reactors
Breeding
220100 - Nuclear Reactor Technology- Theory & Calculation