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

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...

AI Technical Summary

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 cross flow on the rod drop time cannot be simulated; 2) the cross flow has a single form and cannot simulate the upper Flow characteristics of coolant cross flow at different positions of the chamber

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