Cross flow testing apparatus and method for cold test on drive wires of nuclear power plants

A technology of cold state test and test device, which is applied in nuclear power generation, nuclear engineering, nuclear reactor monitoring, etc., can solve the problems of single lateral flow form, cannot simulate the flow characteristics of coolant lateral flow, and cannot simulate the influence of lateral flow, etc., and achieves optimization. design effect

Active Publication Date: 2013-11-20
中广核工程有限公司 +1
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Problems solved by technology

However, the use of the above-mentioned cross flow test device has the following defects: 1) most of the cross flow cannot flow into the control rod guide cylinder assembly 18, so the influence of the

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  • Cross flow testing apparatus and method for cold test on drive wires of nuclear power plants
  • Cross flow testing apparatus and method for cold test on drive wires of nuclear power plants
  • Cross flow testing apparatus and method for cold test on drive wires of nuclear power plants

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Embodiment Construction

[0034] In order to make the purpose of the invention, technical solution and beneficial technical effects of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific implementation methods. It should be understood that the specific implementations described in this specification are only for explaining the present invention, not for limiting the present invention.

[0035] see figure 2 , the cross-flow test device of the nuclear power plant driving line cold state test of the present invention includes a cross-flow restrictor 20, a cross-flow inlet joint 22 and an outlet joint (not shown).

[0036] The transverse flow restrictor 20 is arranged between the upper cylinder body 30 of the pressure vessel and the control rod guide cylinder (not shown), the bottom of which is detachably connected and fixed on the upper core plate 36 by bolts 34, and the height of the top is slightly hig...

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Abstract

The invention discloses a cross flow testing apparatus and method for a cold test on drive wires of nuclear power plants. The testing apparatus comprises a cross flow limiter, a cross flow inlet connecting tube and an outlet connecting tube, wherein the cross flow limiter is removably arranged between an upper barrel of a pressure vessel and a control rod guide cylinder, and the cross flow inlet connecting tube after passing through the upper barrel of the pressure vessel extends to the inside of the cross flow limiter. According to the device and the method, through arranging the removable cross flow limiter between the upper barrel of the pressure vessel and the control rod guide cylinder, the cross flow limiter relatively conforms to actual situations; through replacing the cross flow limiters which are different in structures, the influence of the cross flow limiter on the rod falling time of a control rod assembly can be determined according to different needs, thereby enabling an operation of optimizing a drive wire design by test results to be possible.

Description

technical field [0001] The invention relates to a cold state test of a drive line of a reactor control rod in a nuclear power plant, and more specifically, the invention relates to a transverse flow test device and a test method for a drive line cold test. Background technique [0002] In nuclear power plants, the change of core reactivity is controlled by the reactor control rod drive line, specifically, the control rod drive mechanism arranged on the upper part of the reactor pressure vessel is used to drive the control rod assembly to move up and down in the core through the drive rod. to control rapid changes in core reactivity. The reactor control rod drive line adjusts the reactor power during normal operation, and quickly introduces negative reactivity under accident conditions, which is an important guarantee for the emergency shutdown of the reactor and the safe operation of the nuclear power plant reactor. Therefore, it is necessary to verify the reliability of th...

Claims

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Application Information

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IPC IPC(8): G21C17/10
CPCY02E30/30
Inventor 于晓雷段远刚戴长年刘言午张平唐茂朱明莉
Owner 中广核工程有限公司
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