Creation of a computer program to calculate the Dancoff factor for fuel grids

Automatic translation: In the nuclear reactors of the types built so far, the Fission neutrons slowed down by collisions with the materials present in the reactor. In thermal and epithermal reactors there are even thermal neutrons the main carriers of the nuclear reaction. during deceleration becomes part of the neutrons of different materials absorbed. If this absorption is undesirable, it will called ''parasitic absorption''. A measure of the probability of absorption is the absorption cross section O_a. The absorption cross section is a complicated one Function of the energy with which a neutron hits a nucleus that is in a state of thermal motion. Some materials exhibit in certain energy ranges much higher probability of absorption, the so-called resonance absorption, on. This phenomenon is due to the structure of the nucleus and has not yet been fully clarified. Experimental data serve as the basis for calculating the resonance absorption. The accuracy of the calculations depends to a large extent on these values.