Self-tightening sealed structure for refueling water level control of reactor

Abstract

The invention provides a self-tightening sealed structure for refueling water level control of a reactor. The structure comprises a heat-insulated lining sleeve pipe, a transmission connecting rod, a connecting rod end cap and an adapter pipe end cap, wherein the heat-insulated lining sleeve pipe is arranged in an outlet adapter pipe, and the adapter pipe end cap is installed at one end, far away from a reactor core hanging basket, of the outlet adapter pipe. One end of the transmission connecting rod is connected with one end of the heat-insulated lining sleeve pipe to form a rigid whole, the other end of the transmission connecting rod penetrates through the adapter pipe end cap, and the connecting rod end cap is installed at one end, penetrating through the adapter pipe end cap, of the transmission connecting rod and connected with the adapter pipe end cap in a sealed mode through a sealing structure. A threaded sleeve is sleeved at one end, close to the connecting rod end cap, of the transmission connecting rod, and the outer side of the threaded sleeve is connected with the adapter pipe end cap through threads to form a driving pair. A sealing gasket is further arranged between the transmission connecting rod and the threaded sleeve, and a damping spring is arranged in the connecting rod end cap. The self-tightening sealed structure for the refueling water level control of the reactor achieves taking and releasing of the hanging basket and maintains the refueling water level unchanged in the refueling process to enable the refueling to be carried out safely, provides good sealing effect during the normal operation of the reactor, and is simple in structure and economical.

Description

technical field [0001] The invention relates to a nuclear reactor refueling water level control structure, in particular to a nuclear reactor self-tightening seal type refueling water level control structure, especially suitable for the type of reactor that needs to remove the exit channel to realize the lifting of the hanging basket, such as a supercritical water-cooled reactor . Background technique [0002] The working temperature and working pressure of existing pressurized water reactors are relatively low (the temperature is generally less than 300°C, and the pressure is generally less than 20MPa). The mature domestic material 508-III steel can already meet the performance requirements of the core fluid outlet connection material. There is no need to set a thermal insulation lining sleeve in the outlet connection. Therefore, the existing pressurized water reactor generally adopts a simple outlet connecting pipe, that is, there is no heat-insulating inner sleeve and ot...

AI Technical Summary

Problems solved by technology

[0003] However, in other types of reactors with harsh operating conditions, such as supercritical water-cooled reactors, due to the very harsh operating conditions (working pressure 25MPa, temperature 500~650°C), if the same simple outlet as the existing pressurized water reactor is adopted There are very high performance requirements for outlet connection materials that directly withstand the working pressure and temperature. At present, there is no mature material that can meet this performance requirement.

Therefore, the simple outlet connecting pipe can no longer meet the functional requirements of the supercritical water-cooled reactor, and it is necessary to install a heat-insulating inner sleeve in the outlet connecting pipe

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