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Issue Date: 1-Dec-2016
Title: Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients
Authors: Colton, Ashlea V. K.
Publisher : University of Ontario Institute of Technology
Degree : Master of Science (MSc)
Department : Modelling and Computational Science
Supervisor : Nichita, Eleodore
Keywords: Reactor physics
Diffusion theory
Heavy water reactors
Natural uranium
Core reflector interface
Abstract: To model the neutronic physics behavior of the core in CANDU pressure tube type heavy water reactors with natural-uranium fuel, two levels of calculations are required. Initially, lattice-level transport calculations are carried out to obtain, with high detail and accuracy, the flux distribution inside the lattice cell and composition of the nuclear fuel. Lattice calculations use many (30- 180) energy groups and detailed geometric information to model the fuel channel and the fuel contained within. Once the lattice calculations are complete, the fuel compositions obtained can be used to generate cell-homogenized macroscopic cross-sections condensed to two energy groups, for use in full-core diffusion calculations. Two-group cell-homogenized cross-sections work to acceptable levels of accuracy in most full-core configurations. However, challenges appear when modelling the neutron flux at the fuel-reflector interface (at the boundary of the reactor). This work aims to improve the neutron flux estimates obtained in three-dimensional diffusion calculations by using diffusion coefficients fitted to transport results. It will be shown that significant improvements (>10%) can be made for modeling the neutron physics at the core-reflector interface.
Appears in Collections:Electronic Theses and Dissertations (Public)
Faculty of Science - Master Theses

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