BUNDLEG - a computation code for the fuel element cluster geometry

The code BUNDLEG, a computation code for the fuel element cluster geometry, can evaluate the elements' disposal in the fuel bundle, the areas, the contour of plunged regions and the position of gravity centers of subchannels in the bundle. The computation can be done for any orientation of the bundle in the pressure tube and any fuel bundle possibly used in CANDU type reactors, constituted of elements disposed in four concentrical circles. The code was achieved in the frame of the Romanian project for SEU 43 fuel clusters. The assumptions regarding the bundle geometry are listed. The following data are necessary as imputing data: - the number of element types; - the number of circles corresponding to each element type (except for the last type, for which the remnant number of circles up to four is taken); - the diameter of each element type; - spacers' tolerance, i.e., the maximum separation for which two different value of the spacer's heights are considered as equal; - variation step for the radii of the last three circles of disposal; - the minimal value for the spacers' heights; - the angle α between the pressure tube symmetry and bundle axes. The output quantities are: - the values of the seven spacers; - the radii of the last three circles of disposal; - distinct values of the spacers, calculated from the spacers' average; - the height values of the E, B, welding spot, slide, and error; - the subchannel areas and perimeters