| 摘要 |
The invention relates to nuclear engineering, and more particularly to steam generators for nuclear power plants. The aim of the present invention is to create a steam generator which provides for high capacity heat removal from a reactor, and greater reliability, lower size and specific weight characteristics, and better cost/performance indicators of the steam generator compared to the known prior art. The technical result of the proposed invention is a decrease in thermohydraulic inequality in a steam generator, better filling of the steam generator with heat exchange tubes and better organization of the economizer portion of the heat exchange surface in the steam generator, and a reduction in the concentration of corrosive impurities in the region of the weld seam between the primary loop headers and the horizontal housing. In order to solve the problem of interest in a steam generator comprising a horizontal housing, a primary loop inlet header, a primary loop outlet header, heat exchange tubes and a feedwater dispensing device, the heat exchange tubes of the steam generator are arranged in vertical planes and the inlet and outlet headers of the primary loop are arranged horizontally. It is also proposed to equip the steam generator with at least two primary loop outlet headers. Also proposed is an embodiment in which the feedwater dispensing device is disposed below the heat exchange tubes of the steam generator. |
