Abstract
The original concept of the boiling water reactor core with the reduced moderation of neutrons is proposed, in which a negative void reactivity effect is provided not by increase leakage of neutrons in the axial direction, but by an another physical principle. Instead of the traditional core flattening, a special heterogeneous arrangement is proposed, in which, along with tight lattice fuel assemblies (fuel rod diameter is 13.5 mm, the distance between the fuel rods is 1.3 mm) containing uranium-plutonium (MOX) fuel, there are fuel assemblies with uranium-thorium fuel (UO2+ThO2) with a small (~1 %) initial content of 233U or 235U and an increased water-fuel ratio (fuel rod diameter is 12.6 mm, the distance between the fuel rods is 2.2 mm). Uranium-thorium assemblies provide a negative component of the reactivity effect during dehydration of the core. The results of the calculation of the reactor with a capacity of 3000 MW (t) showed the possibility of achieving a breeding ratio of fuel within 0.96-1.0 with a negative void reactivity effect (-0.2 %). The main advantages of the proposed concept are a directcircuit scheme, medium technological parameters close to traditional boiling reactors, allowing the use of available construction materials and equipment.
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