Unstructured Grids and the Multigroup Neutron Diffusion Equation

<table>(a) Mesh and thermal flux distribution. (b) Power and fluxes. (c) Flux distribution <svg height="20.325001" id="M438" style="vertical-align:-6.53424pt" version="1.1" viewbox="0 0 53.25 20.325001" width="53.25" xmlns="http://www.w3.org/2000/svg" xmlns:xlink="http://www.w3.org/1999/xlink">
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</svg> along the <svg height="7.9499998" id="M439" style="vertical-align:-0.1638pt" version="1.1" viewbox="0 0 9.625 7.9499998" width="9.625" xmlns="http://www.w3.org/2000/svg" xmlns:xlink="http://www.w3.org/1999/xlink">
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</svg>-axis. (d) Flux distribution <svg height="20.325001" id="M440" style="vertical-align:-6.53424pt" version="1.1" viewbox="0 0 54.599998 20.325001" width="54.599998" xmlns="http://www.w3.org/2000/svg" xmlns:xlink="http://www.w3.org/1999/xlink">
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</svg> along the diagonal.</table>

Science and Technology of Nuclear Installations

Unstructured Grids and the Multigroup Neutron Diffusion Equation

Figure 16