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Treatment method, system and product for with radioactive devices of nuclear power station

A disposal method and radioactive technology, which is applied in the field of nuclear power, can solve the problems of occupying the storage space for radioactive machine repairs and affecting daily maintenance operations, and achieve the effects of avoiding potential exposure risks, increasing economic and social benefits, and reducing space occupation

Active Publication Date: 2020-06-05
LINGDONG NUCLEAR POWER +5
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The main shortcomings of this technical solution are as follows: 1. The Ministry of Environmental Protection of the People's Republic of China stipulates that the radioactive solid waste storage needs to establish corresponding waste temporary storage facilities, and simultaneously store The maximum lifespan is 5 years, and the original technical scheme needs to adopt other schemes for disposal after reaching the temporary storage period; 2. With the scheme of temporary storage and disposal, 20 spent fuel grids and their packaging materials will occupy about 300m 3 will occupy the storage space of radioactive machine repair, decontamination and storage workshops, seriously affecting the daily maintenance operations in this area; 3. Although the decontamination methods such as high-pressure water washing are adopted in this plan, the spent fuel grid still has certain Radioactive, presenting a potential exposure risk to personnel working in the area

Method used

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  • Treatment method, system and product for with radioactive devices of nuclear power station
  • Treatment method, system and product for with radioactive devices of nuclear power station
  • Treatment method, system and product for with radioactive devices of nuclear power station

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Embodiment 1

[0067] Please refer to figure 2 , a schematic diagram of a disposal method for nuclear power plants with radioactive devices according to an embodiment of the present invention, including a dismantling step S10, a cutting and sorting step S20, a decontamination step S30, and a melting step S40. A radioactive dose detection step S50 may be included. Specific instructions are given below.

[0068] The radioactive device described in the embodiment of the present invention is described by taking the spent fuel grid as an example. For those skilled in the art, all radioactive contaminated devices in nuclear power plants can use the radioactive device used in nuclear power plants according to the present invention. method for processing. The grids mentioned in this article refer to the spent fuel grids with radioactivity to be processed.

[0069] Such as image 3 , before the dismantling step S10, you can choose to carry out the transfer step S00. The transfer step S00: transf...

Embodiment 2

[0112] see Figure 23 , an embodiment of the present invention provides a disposal system with radioactive devices for nuclear power plants, including a dismantling module 101, a cutting and sorting module 102, a decontamination module 103, and a smelting module 104;

[0113] The dismantling module is used to dismantle the radioactive device to be disposed to obtain various components of the radioactive device to be disposed.

[0114] The cutting and sorting module is used for cutting and sorting according to the preset specifications and sizes corresponding to each component, so as to obtain parts with corresponding specifications and sizes.

[0115] The decontamination module is used to decontaminate the loose parts of each corresponding specification and size to obtain the corresponding materials.

[0116] The smelting module is used to smelt the reusable metal in the material, and solidify the non-reusable metal in the material.

[0117] In one of the possible implementa...

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Abstract

The invention discloses a treatment method, system and product for radioactive devices of a nuclear power station. The method comprises a disassembling step, a cutting and sorting step, a decontamination step and a smelting step. In the disassembling step, a radioactive to-be-treated device is disassembled, all parts of the radioactive to-be-treated device are obtained, in the cutting and sortingstep, cutting and sorting are conducted according to the preset specification and size corresponding to each part so that spare parts with corresponding specifications and sizes are obtained, in the decontaminating step, the spare parts with the corresponding specifications and sizes are decontaminated to obtain corresponding materials, in the smelting step, a reusable metal is melt in the materials and curing treatment is carried out on a non-reusable metal in the materials. Volume reduction treatment of the radioactive contaminated device in the nuclear power station is achieved through thedecontamination step and the cutting and sorting step, and an occupied space is reduced. Through the decontamination step and the smelting step, reuse of materials is achieved, and the big problem that radioactive contaminated devices are difficult to dispose is solved.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a disposal method, system and product for nuclear power plants with radioactive devices. Background technique [0002] A spent fuel grid is a device used to store spent fuel assemblies discharged from the core of a nuclear power plant, new fuel assemblies, control rod assemblies, and damaged fuel assemblies. The early spent fuel grid neutron absorbing material used cadmium metal, and the sleeve size was large, which could accommodate 36 fuel assemblies. Its structure is as figure 1 As shown, it is mainly composed of a lower support plate, an upper support plate, a hoarding plate, a sleeve, a foot and connecting fasteners. The new spent fuel grid uses aluminum-based boron carbide as the neutron absorbing material. A spent fuel grid can accommodate 56 sets of fuel assemblies. In order to store more spent fuel assemblies in the spent fuel pool, some power plants use A trans...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/30G21F9/00
CPCG21F9/30G21F9/308G21F9/001
Inventor 刘省勇张文利谢建华何英勇
Owner LINGDONG NUCLEAR POWER