Critical Experiments with the UO₂-2 wt.% PuO₂ Batch Core in the PRTR

Technical Report · Mon Feb 01 00:00:00 EST 1971

DOI:https://doi.org/10.2172/4071718· OSTI ID:4071718

Smith, R. I. ^[1]; Kutcher, J. W. ^[1]; Lauby, J. H. ^[1]; Williams, L. D. ^[1]

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1. Battelle Pacific Northwest Labs., Richland, WA (United States)

The initial phase of the Batch Core Experiment comprised the loading of a new core of UO₂-2 wt.% PuO₂ fuel elements and the performance of a series of critical tests to determine the physics parameters of this new core. Measurements included the critical loadings for boron concentrations ranging from zero to about 21 parts per million by weight (wppm) of ¹⁰B in the D₂O moderator, moderator level coefficients of reactivity over a 25-inch range of moderator heights at several horon concentrations, moderator void worths, thermal neutron flux distributions within the core, the effect of loss of coolant from fuel channels, fuel element worths, and kinetics parameters. The results of these measurements are presented in this report. At specified burnup levels during the Batch Core Experiment, interim critical tests were conducted. These tests included measurements of core excess reactivity, fuel element worths, poison rod worths, and kinetics parameters. The results of these measurements are also presented in this report.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(45-1)-1830
• OSTI ID: 4071718
• Report Number(s): BNWL-1553
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Batch Core Experiment
Boron
CONFIGURATION
CRITICALITY
Concentrations
Coolant
Core Experiment
Criticality
DISTRIBUTION
Fuel Channels
Fuel Elements
Kinetics
N38110* --Power Reactor Development--Kinetics & Dynamics
N38110* --Power Reactor Development--Kinetics & Dynamics
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM OXIDES
POISONING
PRTR
Performance
Poison
REACTIVITY WORTHS
REACTOR CORE
REACTOR KINETICS
TEMPERATURE COEFFICIENT
THERMAL NEUTRONS
URANIUM DIOXIDE
VOID COEFFICIENT