Concept Selection and Neutronic Characteristics of Nuclear Icebreaker Cores

Abstract

The developmental history of the series-produced core for nuclear icebreakers and its conceptual and structural designs and the computational-methodological base of the physical design are presented. The fundamental differences from VVER-type power reactor cores, which are due to the specific operating conditions of ice breakers, are discussed. Measurements of the basic neutronic characteristics of a series-produced icebreaker core are presented and compared with calculations performed with the tested software system VKN-02. Experimental data confirm that the accuracy of the VKN-02 system in calculating the neutronic characteristics determining nuclear safety and the thermal engineering reliability of an icebreaker core is acceptable.