DOI: 10.55176/2414-1038-2019-2-107-116
Authors & Affiliations
Pivovarov V.A.
Scientific and Engineering Centre for Nuclear and Radiation Safety, Moscow, Russia
Pivovarov V.A. – Leading Researcher, Cand. Sci. (Phys.-Math.), Scientific and Engineering Centre for Nuclear and Radiation Safety. Contacts: bld. 5, 2/8, Malaya Krasnoselskaya st., Moscow, Russia, 107140. Tel.: +7 (903) 811-64-70; e-mail:
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). Urani-um-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 direct-circuit scheme, medium technological parameters close to traditional boiling reactors, allowing the use of available construction materials and equipment.
Keywords
light-water boiling reactor, tight lattice fuel assembly, fast neutron spectrum, neutronic characteristics
Article Text (PDF, in Russian)
UDC 621.039