Migration transfer characteristic test system of fragments of reactor containment and test method thereof

Abstract

The invention relates to a migration transfer characteristic test system of fragments of a reactor containment and a test method thereof. The system comprises a test segment module composed of a waterchannel, a rectifying grid, a filter screen and related equipment, a flow rate adjusting module composed of a water tank, a main water pump, an electric valve and related pipelines and instruments, acooling module composed of a cooling water pump, a heat exchanger, a cooling tower and related pipelines and instruments, a thermotechnical hydraulic parameter measuring module composed of a flowmeter, a temperature sensor, a pressure sensor and a liquidometer, an image collecting module composed of a high-speed camera, a local area network computer and related image processing software, a flow field information collection module composed of PIV equipment, a local area network computer and related flow field processing software and a remote control module composed of a programmable logic controller, a water pump, an electric valve and related equipment. The system simulates a ground water flow velocity field of the containment accurately after loss of coolant accident and acquires characteristic parameters of different fragments migrating in water.

Description

technical field [0001] The invention belongs to the technical field of nuclear power equipment performance verification test research, and in particular relates to a nuclear reactor containment fragment migration characteristic test system and a test method thereof. Background technique [0002] When a loss of water accident (LOCA) occurs in a pressurized water reactor nuclear power plant, the thermal insulation material wrapped outside the primary circuit pipe of the coolant system and other materials near the breach are damaged and fall off due to the impact of the high-energy jet at the breach. The generated debris will be scattered throughout the containment vessel, and migrate to the containment pit along with the water flow from the breach, which may cause blockage of the pit filter and further cause recirculation cooling failure. In the 1990s, some operating nuclear power plants in the world had clogged pit filters, which caused serious economic losses and potential s...

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Problems solved by technology

[0006] The purpose of the present invention is to provide a nuclear reactor containment fragment migration characteristic test system and its test method for the above-mentioned test device or test system that is not applicable or does not meet the requirements of the nuclear engineering field for the experimental research on the migration characteristics of containment fragments. The device and system described above can realize the visual research on the migration characteristics of fragments in the test section, and at the same time can achieve simple and fast adjustment of system parameters, and can obtain test parameters such as flow rate, pressure, temperature, etc., and use PIV technology to give detailed flow information in the test section. Field information for in-depth study of fragment migration characteristics

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