Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator

Technical Report · Mon Dec 01 00:00:00 EST 1986

DOI:https://doi.org/10.2172/10132997· OSTI ID:10132997

Bierman, S R

The results obtained in a series of criticality experiments performed as part of a joint program on criticality data development between the United States Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan are presented in this report along with a complete description of the experiments. The experiments involved lattices of Fast Test Reactor (FTR) fuel pins in an organic moderator mixture similar to that used in the solvent extraction stage of fuel reprocessing. The experiments are designed to provide data for direct comparison with previously performed experimental measurements with water moderated lattices of FTR fuel pins. The same lattice arrangements and FTR fuel pin types are used in these organic moderated experimental assemblies as were used in the water moderated experiments. The organic moderator is a mixture of 38 wt % tributylphosphate in a normal paraffin hydrocarbon mixture of C{sub 11}H{sub 24} to C{sub 15}H{sub 32} molecules. Critical sizes of 1054.8, 599.2, 301.8, 199.5 and 165.3 fuel pins were obtained respectively for organic moderated lattices having 0.761 cm, 0.968 cm, 1.242 cm, 1.537 cm and 1.935 cm square lattice pitches as compared to 1046.9, 571.9, 293.9, 199.7 and 165.1 fuel pins for the same lattices water moderated.

• 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: 10132997
• Report Number(s): PNL--5803; ON: DE94007613
• Country of Publication: United States
• Language: English

Related Subjects

050800
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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42 ENGINEERING
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CONSOLIDATED FUEL REPROCESSING PROGRAM
COORDINATED RESEARCH PROGRAMS
CRITICALITY
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LMFBR TYPE REACTORS
Nuclear Criticality Safety Program (NCSP)
ORGANIC MODERATORS
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REACTOR LATTICES
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SOLVENT EXTRACTION
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SPENT FUELS REPROCESSING
US DOE