Cuboid sodium-sodium-water integrated steam generator

Abstract

The invention relates to the technical field of nuclear power plant steam generators and particularly disk a cuboid sodium-sodium-water integrated steam generator. A barrel in the steam generator is of a cuboid shell structure. The upper end of the barrel is provided with an upper tube plate. A plurality of sodium-water heat transfer tubes are arranged in the barrel. The two ends of the sodium-water heat transfer tubes are arranged on a left half plane and a right half plane of the upper tube plate correspondingly. The upper end of the barrel is provided with an upper sealing head. The upper sealing head and the upper tube plate are divided into two independent spaces, namely, a steam chamber and a water supply chamber, through a vertical partition board, and the steam chamber and the water supply chamber communicate with two ports of each sodium-water heat transfer tube. The sodium-water heat transfer tubes are arranged in the barrel. The outer sidewall of the barrel is provided withan encircling plate. One ports of the sodium-water heat transfer tubes on the sidewall of the barrel are enclosed to form primary sodium inlets. The encircling plate encloses the other ports of the sodium-water heat transfer tubes to form primary sodium outlets. The steam generator provided by the invention improves the heat transfer efficiency. The number of sodium circulation processes is reduced to one. The resistance in the technological process is obviously reduced.

Description

technical field [0001] The invention belongs to the technical field of steam generators for nuclear power plants, and in particular relates to a cuboid sodium-sodium-water integrated steam generator. Background technique [0002] The main heat transfer system of the sodium-cooled fast reactor, that is, the system for generating steam, is composed of two loops, namely, the primary loop, the secondary loop, and the steam generator. The primary circuit is composed of a primary sodium circulation pump, pipelines, and an intermediate heat exchanger. The nuclear energy generated by the reactor in the reactor vessel is transferred to the intermediate heat exchanger secondary sodium circuit through the circulation driven by the primary sodium circulation pump. The secondary loop consists of an intermediate heat exchanger, a secondary loop sodium circulation pump, a buffer tank, a sodium distribution pipe, a steam generator and a superheater. The heat of the sodium in the secondary ...

AI Technical Summary

Problems solved by technology

High engineering cost

(3) The intermediate heat exchanger is usually installed in the stack container, which is difficult to install, and it is in the environment of high neutron radiation all the year round

(4) Two sodium circulation processes are required, the heat transfer efficiency is low, and the operation is complicated

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