Abstract
This work demonstrates an approach to determine probability of perturbation of the axial profile of the thermal neutron flux in the Advanced Test Reactor. The axial flux profile is expected to follow a theoretical cosine shape, due to the minimal use of vertically-withdrawn shims. Reactivity is normally controlled by rotation of Outer Shim Control Cylinders, uniformly affecting neutron flux at all axial locations. The Advanced Test Reactor routinely accepts for irradiation experiments of a variety of designs. Among the analyses required by the safety basis approved by the United States Department of Energy is the characterization of a new experiment’s potential for perturbing the axial flux, which could exacerbate power peaking in the driver fuel. However, this perturbation can be more or less severe in different locations within the fuel. Therefore, the best characterization of axial flux perturbation requires knowledge of baseline axial flux. Such information is obtained by measuring decay in activated uranium flux wires irradiated at known positions in cooling channels in plate-type fuel elements. Due to variability in measured axial flux, it is not usually clear whether a given anomalous measurement is caused by an actual perturbation. Assuming normality in random measurement errors, the probability of an actual perturbation is quantified.
Highlights
The ATR core consists of forty (40) plate-type fuel elements, of aluminum-clad highlyenriched uranium
Most of the flux traps include the additional advantage of an in-pile tube, isolated from the reactor primary coolant system, which allows a given experiment to be irradiated at temperature, pressure, and chemistry conditions selected by the sponsor
The four other flux traps are known as outer flux traps, for being outside the closed fuel serpentine, and are designated by cardinal directions (North (N), West (W), East (E), and South (S))
Summary
The ATR core (see Figure 1) consists of forty (40) plate-type fuel elements, of aluminum-clad highlyenriched uranium. Pressurized water is both the moderator and the primary coolant and flows downward through the fuel element channels. The purpose of localized power control is to simultaneously irradiate multiple experiments in the various flux traps, at programmable power levels. Most of the flux traps include the additional advantage of an in-pile tube, isolated from the reactor primary coolant system, which allows a given experiment to be irradiated at temperature, pressure, and chemistry conditions selected by the sponsor. The axial flux profile can be measured, as described below By taking these measurements in ATRC, it can be shown what effect a given experiment will have on ATR
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