摘要:
The present invention relates to nuclear technology and is intended for use in power-generating systems with a fast reactor cooled by a liquid-metal coolant which is primarily in the form of molten lead or an alloy thereof. The problem addressed by the invention consists in reducing the specific volume of lead coolant per unit of power of the reactor and in increasing the safety of the reactor. The system comprises a reactor cavity (1) with an upper cover (2), an arranged within the cavity (1) reactor having an active zone (4), steam generators (5), circulation pumps (7), circulation conduits (8) and (9), actuating mechanism systems and devices for starting up, operating and shutting down the reactor system, wherein the steam generators (5) are in the form of tubular heat exchangers in which the lead coolant (10) flows within the pipes, while the water-steam flows in a space between the pipes, the steam generators (5) are arranged in separate boxes (6) and communicate with the reactor cavity (1) by means of circulation conduits for raising (8) and discharging (9) the lead coolant (10), the steam generators (5) and most of the circulation conduits (8) and (9) are arranged higher than the level of the lead coolant (10) within the reactor cavity (1), and the circulation pumps (7) are arranged within the reactor cavity (1) on the circulation conduits (8) and (9) for raising the "hot" lead coolant, and a technical means (13) is provided for ensuring intrinsic circulation of the lead coolant (10) through the active zone (4) when the circulation pumps (7) are switched off.
摘要:
An active zone of a reactor, a fuel element and a fuel assembly for creating said active zone are intended for use in fast reactors with a nitride fuel and a liquid-metal coolant primarily in the form of molten lead and alloys thereof. The problem addressed by the invention consists in creating an active zone with a void reactivity effect and with effective power flattening along the radius of the active zone. The active zone comprises a homogeneous uranium-plutonium nitride fuel, the mass fraction of which in the active zone is a minimum 0.305, and consists of 3 parts - a central part, an intermediate part and a peripheral part which form fuel assemblies comprising fuel elements with geometrically identical shells but with a differing height of the fuel column in the central part, the intermediate part and the peripheral part of the active zone, wherein the radial distribution of the fuel across the volume of the active zone is characterized by a stepped shape in a longitudinal section. The radius of the central part of the active zone is from 0.4 to 0.5 of the effective radius of the active zone, while the height of the fuel column in the fuel elements of the fuel assemblies in the central part is from 0.5 to 0.8 of the height of the fuel column in the fuel elements arranged in the fuel assemblies in the peripheral part of the active zone. The heights of the fuel columns forming a stepped intermediate part (with at least one step) for diameters ranging from 0.5 to 0.85 of the effective diameter of the active zone are selected within the range from 0.55 to 0.9 of the height of the fuel column in fuel elements arranged in the fuel assemblies in the peripheral part of the active zone.