Criticality Experiments with Units of LWR-Type Fuel Rods Submerged in Water and Separated by Neutron Flux Traps

Conference · Sun Jun 12 04:00:00 EDT 1988 · Transactions of the American Nuclear Society

OSTI ID:6900800

Bierman, S. R. ^[1]

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

A series of criticality experiments to provide benchmark-type data on neutron flux traps has been completed at the US Department of Energy Hanford Critical Mass Laboratory, operated by the Pacific Northwest Laboratories of Battelle Memorial Institute. The experiments were funded by the Sandia National Laboratory and are designed to simulate transport environments and high-density fuel storage facilities. the experimental assemblies consisted of 2 ˙ 2 arrays of 4.31 wt% ²³⁵U-enriched UO₂ fuel rods arranged in water on a 1.891-cm² center-to-center spacing. This lattice spacing results in a moderator-to-fuel volume ratio of 1.6 which approximates that found typically in boiling water reactors and in pressurized water reactors. Each assembly consisted of four, near equally sized units of fuel rods separated by a neutron flux trap and varying amounts of moderator.

• 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: 6900800
• Report Number(s): PNL-SA-15457; CONF-880601-46; ON: DE88014908
• Conference Information: Journal Name: Transactions of the American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
Assembly
BWR TYPE REACTORS
Benchmark-Type Data
Criticality Experiments
DATA
FUEL ELEMENTS
FUEL RODS
Fuel Rods
INFORMATION
NEUTRON FLUX
NUMERICAL DATA
Neutron Flux Trap
Neutron Flux Traps
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTORS
SPENT FUEL STORAGE
STORAGE
STORAGE FACILITIES
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS