Criticality experiments with mixed oxide fuel pin arrays in plutonium-uranium nitrate solution
- Pacific Northwest Lab., Richland, WA (United States)
- Oak Ridge National Lab., TN (United States)
A series of critical experiments was completed with mixed plutonium-uranium solutions having a Pu/(Pu + U) ratio of approximately 0.22 in a boiler tube-type lattice assembly. These experiments were conducted as part of the Criticality Data Development Program between the United States Department of Energy (USDOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of the experiments and data are included in this report. The experiments were performed with an array of mixed oxide fuel pins in aqueous plutonium-uranium solutions. The fuel pins were contained in a boiler tube-type tank and arranged in a 1.4 cm square pitch array which resembled cylindrical geometry. One experiment was perfomed with the fuel pins removed from the vessel. The experiments were performed with a water reflector. The concentration of the solutions in the boiler tube-type tank was varied from 4 to 468 g (Pu + U)/liter. The ratio of plutonium to total heavy metal (plutonium plus uranium) was approximately 0.22 for all experiments.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5113075
- Report Number(s):
- PNL-6559; ON: DE94007612
- Country of Publication:
- United States
- Language:
- English
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Criticality Experiments with Mixed Plutonium and Uranium Nitrate Solution at a Plutonium Fraction of 0.2 and 1.0 in Annular Cylindrical Geometry
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·
Thu Mar 31 23:00:00 EST 1988
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OSTI ID:1070037
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Sun Nov 30 19:00:00 EST 1986
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OSTI ID:10133001
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CONSOLIDATED FUEL REPROCESSING PROGRAM
COORDINATED RESEARCH PROGRAMS
CRITICALITY
DATA
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
FUELS
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JAPANESE ORGANIZATIONS
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LMFBR TYPE REACTORS
MATERIALS
MEASURING METHODS
METALS
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NATIONAL ORGANIZATIONS
NUCLEAR FUELS
NUMERICAL DATA
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM
PNC
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
SOLID FUELS
SPENT FUELS
TEST REACTORS
TRANSURANIUM ELEMENTS
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