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Disassembling technology and dedicated disassembling device of detector assemblies

A detector assembly and mobile detector technology, which is applied in nuclear engineering, reactor fuel elements, reactors, etc., can solve the problems of a large number of personnel radiation and excessive environmental dose, and achieve reasonable process design, good radiation protection, and shortened dismantling time. Effect

Active Publication Date: 2018-03-06
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, in the existing technology, when the entire detector assembly is pulled out from the upper reactor internals, due to the high radioactivity at the lower end of the detector assembly, the environmental dose during the extraction process exceeds the standard, resulting in the problem that personnel are exposed to a large amount of radiation.

Method used

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  • Disassembling technology and dedicated disassembling device of detector assemblies
  • Disassembling technology and dedicated disassembling device of detector assemblies
  • Disassembling technology and dedicated disassembling device of detector assemblies

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Embodiment

[0035] Such as Figure 1 to Figure 6 As shown, the present invention is the dismantling process and special dismantling equipment of the detector assembly introduced from the pressure vessel top cover during the non-full life of the nuclear power plant. During refueling, the detector assembly 5 to be dismantled is accompanied by the upper reactor internal 19 and the measurement guide structure 18 in the stack are stored in the refueling pool 7 together. There are 5 groups of four dismantled detector assemblies, a total of 12 groups are distributed on the outer edge of the upper internals 19. At this time:

[0036] —The internals hanger is disconnected from the upper internals 19, and transferred to the vacant position of the reactor building operation platform 1;

[0037] —The inner fuel assembly of the reactor pressure vessel assembly 2 has been shipped out to the spent fuel pool;

[0038] - After the loading and unloading machine 16 transfers the high-release container 8 t...

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PUM

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Abstract

The invention discloses a disassembling technology and a dedicated disassembling device of detector assemblies. The disassembling technology comprises the following steps: moving a big and small vehicle assembly, releasing a gripping apparatus, lifting the gripping apparatus after gripping and disassembling one detector assembly, and clamping and cutting off the detector assembly by a shearing andshrinking assembly; putting the end part of the detector assembly into a low-level waste container; driving the detector assembly to rotate by a winding module in the shearing and shrinking assembly,pulling out the detector assembly from a guiding structure under the action of the shearing and shrinking assembly, coiling the detector assembly after winding into a tubular shape, and descending into a temporary storage container; disassembling other detector assemblies in the same group by repeating the steps; moving the big and small vehicle assembly after completing disassembly, winding thedetector assemblies, and descending into high-level waste containers; continuously disassembling detector assemblies in other groups by repeating the steps; recovering components to original storage places after completing the disassembly of all detector assemblies. According to the disassembling technology disclosed by the invention, a whole pull-out process is reasonably designed, the operatingtime is shortened, and good radiation protection is achieved by utilizing the shield of water in a refueling pool.

Description

technical field [0001] The invention relates to a dismantling technology of a detector assembly introduced from the top cover of a pressure vessel during the non-full life of a nuclear power plant, in particular to a detector assembly dismantling process and special dismantling equipment. Background technique [0002] The instruments used in the core measurement system in the second-generation and second-generation pressurized water reactor nuclear power plants are divided into instrument thermocouples for temperature measurement and neutron flux detectors for flux measurement. The thermocouple is introduced from the top cover of the pressure vessel, guided by the thermocouple column assembly, and positioned at the specified measuring point position, and the lower end of the thermocouple is located at the core outlet of the upper core plate. The flux detector is introduced from the bottom head of the pressure vessel, guided through the instrument sleeve and finger sleeve whe...

Claims

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Application Information

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IPC IPC(8): G21C19/02G21C19/105
CPCG21C19/02G21C19/105Y02E30/30
Inventor 李娜安彦波余志伟肖锋钟元章刘昌文罗英朱建军湛卉杨其辉翁松峰陈书华黄有骏张翼肖聪
Owner NUCLEAR POWER INSTITUTE OF CHINA
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