3. NATURE OF PHYSICAL PROBLEM SOLVED
ANDROMEDA is a one-dimensional multigroup diffusion-burnup code for use with fast reactors. The code is designed primarily for preliminary fuel-cycle analysis of fast breeder reactors by performing the following items:
a) Regular flux calculation.
b) Adjoint flux calculation.
c) Material buckling calculation.
d) Kinetic parameter calculation.
e) Searches on material (fuel or poison) concentration or region dimensions.
f) Collapsing the multigroup cross sections into several group cross sections, and punching them on cards, if desired.
All of the items above mentioned except A can be performed at any time during burnup history according to input options. Geometries to deal with are cylinder, slab and sphere. The time interval for burnup calculation is given by input, and for each time interval, reaction rate and mass changes of each isotope, and breeding ratio, burnups in atom percent and power peaking factors in each region are computed. The multigroup cross section library for ANDROMEDA is prepared by LTANDRO, which is able to compose three cross section sets, i.e., JAERI-Fast-Set, ABBN-Set and RCBN Set, on one magnetic tape. It depends on user's choice which cross section set will be used.