Abstract
In the current CANDU full-core physics analysis, the maximum pin power within a bundle is determined by multiplying the bundle power obtained from solving the three-dimensional neutron diffusion equation with a ratio of the highest pin power to the average pin power, obtained from burnup-dependent infinite lattice calculations. Since the geometry of the fuel channel changes during the life of the reactor, the ratio of the highest to the average pin power changes as well. The objective of the current paper is to quantify such variations. Two sources of variation are considered: (i) pressure tube diametral creep (PTDC); and (ii) the placement of the fuel bundle inside the fuel channel in the lattice model. The results from the study indicate that the maximum pin power could vary up to 1.2%, depending on the amount of the PTDC, the fuel burnup, and the fact that a concentric or non-concentric lattice model is used. Therefore, it is recommended that the lattice model used for deriving the form function be as consistent as possible to the core condition being analysed, especially with respect to the PTDC value.
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