Criticality experiments to provide benchmark data on neutron flux traps
The experimental measurements covered by this report were designed to provide benchmark type data on water moderated LWR type fuel arrays containing neutron flux traps. The experiments were performed at the US Department of Energy Hanford Critical Mass Laboratory, operated by Pacific Northwest Laboratory. The experimental assemblies consisted of 2 /times/ 2 arrays of 4.31 wt % /sup 235/U enriched UO/sub 2/ fuel rods, uniformly arranged in water on a 1.891 cm square center-to-center spacing. Neutron flux traps were created between the fuel units using metal plates containing varying amounts of boron. Measurements were made to determine the effect that boron loading and distance between the fuel and flux trap had on the amount of fuel required for criticality. Also, measurements were made, using the pulse neutron source technique, to determine the effect of boron loading on the effective neutron multiplications constant. On two assemblies, reaction rate measurements were made using solid state track recorders to determine absolute fission rates in /sup 235/U and /sup 238/U. 14 refs., 12 figs., 7 tabs.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6915117
- Report Number(s):
- PNL-6205; ON: DE88013957
- Country of Publication:
- United States
- Language:
- English
Similar Records
Criticality Experiments with Units of LWR-Type Fuel Rods Submerged in Water and Separated by Neutron Flux Traps
Criticality Experiments with Units of LWR-Type Fuel Rods Submerged in Water and Separated by Neutron Flux Traps
Power Calibration for BSR Loading 33
Conference
·
Sun Jun 12 00:00:00 EDT 1988
· Transactions of the American Nuclear Society
·
OSTI ID:5490248
Criticality Experiments with Units of LWR-Type Fuel Rods Submerged in Water and Separated by Neutron Flux Traps
Conference
·
Sun Jun 12 00:00:00 EDT 1988
· Transactions of the American Nuclear Society
·
OSTI ID:6900800
Power Calibration for BSR Loading 33
Technical Report
·
Wed Nov 27 23:00:00 EST 1957
·
OSTI ID:4327816
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