Hoop straining beam type supporting device used for reactor pressure vessel

A pressure vessel, hoop tension beam technology, applied in the direction of reactor, nuclear power generation, nuclear engineering, etc., can solve the problem of weak anti-seismic ability, and achieve the effect of simple structure, improved anti-seismic ability, and easy maintenance.

Active Publication Date: 2017-02-08
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The object of the present invention is to provide a hoop and beam-type support device for a reactor pressure vessel. By setting a cross-tension beam and a hoop surrounding the outer surface of the pressure vessel, one end of the cross-tension beam is connected to

Method used

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  • Hoop straining beam type supporting device used for reactor pressure vessel
  • Hoop straining beam type supporting device used for reactor pressure vessel
  • Hoop straining beam type supporting device used for reactor pressure vessel

Examples

Experimental program
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Effect test

Example Embodiment

[0037] Example 1:

[0038] Such as figure 1 , figure 2 , image 3 As shown, a hoop bracing beam type supporting device for a reactor pressure vessel of the present invention includes a concrete foundation 2, a hoop 4 encircling the upper part of the pressure vessel, and at least two sets of transverse bracing beams 7 arranged on the periphery of the pressure vessel. One end of the transverse beam 7 is connected with the hoop 4, and the other end is connected with the concrete foundation 2.

[0039] In the embodiment, the hoop 4 is a well-known device in the field, and its structure and principle are common knowledge in the field, and no further description is given here. The hoop 4 is arranged around or encircling the upper part of the outer surface of the reactor pressure vessel, and the transverse beams 7 are evenly arranged on the hoop 4, which does not limit the axial thermal expansion of the pressure vessel. In this embodiment, the concrete foundation 2 is located in the rea...

Example Embodiment

[0041] Example 2:

[0042] On the basis of the first embodiment, this embodiment further restricts that the transverse beam 7 and the hoop 4 are connected by the connecting pin 1. There are many ways to connect the transverse beam 7 and the hoop 4, such as fixed connection and detachable connection. In this technical solution, it is preferably connected by connecting pin 1. The structure of the connecting pin can be cylindrical pin, tapered pin, or special shape. Pins, etc., can directly determine the mutual position of the connecting hoop 4 and the transverse beam 7 to transmit a small load and realize a tightly adaptable connection. The other structures and principles involved in this embodiment are the same as those in Embodiment 1, and will not be repeated.

Example Embodiment

[0043] Example 3:

[0044] On the basis of the foregoing embodiment, this embodiment further defines that a fastener is installed between the connecting pin 1 and the hoop 4, and the fastener is a connecting piece formed by the detachable connection of the bolt 3 and the nut 5. When the reactor pressure vessel is in operation, both the external load and the load generated by the internal force during operation are relatively large. Therefore, for the high-flux test reactor reactor to avoid unrecoverable flexible swing, the supporting device must also have Strong endurance and strong stability. The main factors affecting the stability of the connection are the components themselves and the stability of the connection between the components. Among them, the materials of the hoop, cross beam, connecting pin and other components are all made of workpieces with certain rigidity or strength, which can meet the supporting requirements Function. In terms of the connection of components...

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PUM

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Abstract

The invention discloses a hoop straining beam type supporting device used for a reactor pressure vessel. The hoop straining beam type supporting device comprises a concrete foundation, a hoop which surrounds the upper part of the pressure vessel, and at least two groups of straining beams oppositely arranged on the periphery of the pressure vessel, wherein one end of the straining beam is connected with the hoop, and the other end is connected with the concrete foundation. According to the device provided by the invention, the structures including the hoop, the straining beam, a connecting pin and the like are adopted, the hoop surrounds the outer surface of the upper part of the pressure vessel, one end of the straining beam is connected with the hoop, the other end is fixed in the concrete foundation of a reactor pit, and the straining beam and the hoop are connected through the connecting pin; while a reactor pressure device is supported, the lateral stress of the pressure vessel in an operation process is decomposed, the flexible swinging of the vessel is eliminated, and the shock resistance of the reactor pressure vessel is enhanced.

Description

technical field [0001] The invention relates to the technical field of support for reactor pressure vessels of nuclear power plants, in particular to a hoop and beam type support device for reactor pressure vessels. Background technique [0002] The reactor pressure vessel is one of the key equipment of the entire nuclear power plant reactor and the primary circuit system, and is an important part of the pressure boundary. structure etc. In the containment, in order to effectively fix the reactor pressure vessel and ensure the safe operation of the entire reactor, a supporting structure must be set. The weight of the entire nuclear power plant reactor is relatively large. The pressure and temperature of the coolant system will change between the operation and shutdown of the entire reactor. At the same time, the influence of seismic load should also be considered. Therefore, the support structure must be able to withstand the static pressure of the pressure vessel. Under t...

Claims

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Application Information

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IPC IPC(8): G21C13/024
CPCG21C13/024Y02E30/30
Inventor 何震陈富财田俊科甘斌谭波杜华罗英
Owner NUCLEAR POWER INSTITUTE OF CHINA
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