| 摘要 |
The invention relates to the electric power industry, and more particularly to horizontal steam generators for nuclear power stations with water-cooled, water-moderated reactors and to a reactor plant with a water-cooled, water-moderated reactor and a horizontal steam generator. The present reactor plant with a water-cooled, water-moderated reactor and a horizontal steam generator comprises: a nuclear reactor with four circulation loops, each of which comprises a steam generator with a horizontal bundle of heat exchange tubes, said tubes being divided into banks by intertube passages and being connected to primary coolant collectors inside a cylindrical housing with ellipsoidal ends; a main circulation pump; and also a main primary coolant circulation pipe. The inside diameter of the housing Dкорп, the transverse distance S between the axes of the primary coolant collectors, and the length of the steam generator Lк along the inside surfaces of the ellipsoidal ends are selected on the basis of the respective given relationships, where: D is the nominal steam capacity of a steam generator (TPH); Nтр is the number of heat exchange tubes in a steam generator housing (pieces); Sв and Sг are the intervals between the heat exchange tubes in a vertical and in a horizontal row of a heat exchange bundle, respectively (mm); k is a feature of the arrangement of a heat exchange bundle in banks; H is the height to which a steam generator housing is filled with tubes (mm); Dкол is the outside diameter of a primary coolant collector in a drilled region (mm); α is the central angle of bend of the heat exchange tubes (degrees); B1 and В2 are the width of the central passage of a heat exchange tube bundle and the width of the passage of a heat exchange tube bundle situated opposite a coolant collector, respectively (mm); Sкол is the circumferential interval of the heat exchange tubes around the outside surface of a coolant collector (mm); Нпто is the area of the heat exchange surface of a steam generator (m2); d is the outside diameter of the heat exchange tubes (mm); Δ is the distance from the outer tube of a heat exchange bundle to the inner surface of an end of a steam generator along the longitudinal axis of the steam generator (mm); wherein the angle of bend of the heat exchange tubes and the distance Δ are selected from the following ranges: 90º≤α≤150º and 300 mm≤Δ≤1000 mm. |
