CONTROL ROD IN A HYDROGEN-COOLED VESSEL REACTOR

摘要

The invention relates to the nuclear technology, especially, to facilities in the control and protective system of water-cooled vessel reactors, and can be used among the control mechanisms realized in the form of rods, either single or integrated to an assembly. The control rod includes an cladding having a neutron absorber stack disposed within the cladding and comprised of two parts, of which one is made of a material having (n, alpha ) reaction with neutrons, for example, of boron carbide. The other part, inserted first into the core, is of a length determined by a mathematical expression including a length of the neutron absorber stack and efficiency values of the control rods with various parameters. A length of the part made of a dysprosium-based material, determined by the above-mentioned mathematical expression, permits to manufacture the rod with a maximum weight, taking into account the change in its absorbing properties resulting from an increase in the specific share of the dysprosium-based material, the density of which is clearly greater than that of boron carbide.