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Online monitoring apparatus for monitoring influence of nuclear power plant containment fragments upon pressure drop of fuel assembly

A nuclear power plant containment and fuel assembly technology, which is applied in the field of nuclear safety, can solve the problems of fuel assembly pressure drop increase, and achieve the effect of preventing clogging and preventing precipitation

Inactive Publication Date: 2017-09-22
NORTH CHINA ELECTRIC POWER UNIV (BAODING)
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

These debris, including some impurities, silt, and foreign matter accumulated in the containment, will enter the containment pit due to the migration of the water flow in the containment after the accident. Although the debris can be captured by the pit filter, it is still Part of the debris will bypass the containment pit screen and enter the primary circuit system, and accumulate and deposit in the core fuel assembly, causing an increase in the pressure drop of the fuel assembly

Method used

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  • Online monitoring apparatus for monitoring influence of nuclear power plant containment fragments upon pressure drop of fuel assembly
  • Online monitoring apparatus for monitoring influence of nuclear power plant containment fragments upon pressure drop of fuel assembly
  • Online monitoring apparatus for monitoring influence of nuclear power plant containment fragments upon pressure drop of fuel assembly

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Embodiment Construction

[0016] The invention provides an online monitoring device for the impact of nuclear power plant containment fragments on the pressure drop of fuel assemblies, which will be described below in conjunction with the accompanying drawings.

[0017] figure 1 Shown is a schematic diagram of the structure of the online monitoring device for nuclear power plant safety. The online monitoring device shown in the figure is that a full-scale fuel assembly 2 is installed in the test section 1; the lower armored thermocouple 6 is inserted in the bottom of the test section 1, the middle armored thermocouple 7 is inserted in the middle, and the upper armored thermocouple is inserted in the upper part. Even 8, the differential pressure gauge 5 at both ends is connected to the upper and lower ends of the test section 1, the upper differential pressure gauge 4 is connected to the upper and middle end of the test section 1, and the lower differential pressure gauge 3 is connected to the middle an...

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Abstract

The invention discloses an online monitoring apparatus for monitoring influence of nuclear power plant containment fragments upon pressure drop of a fuel assembly and belongs to the technical field of nuclear safety. The online monitoring apparatus comprises a test segment, a full-size fuel assembly, an armored thermocouple, a differential pressure gauge, a pressure meter electric V-shaped ball valve, a flow meter, and a stirring water tank. By simulating the fact that fragments from an accident in a pressurized water reactor nuclear power station penetrate a containment pit strainer and comprehensively utilizing the measuring instruments such as a temperature sensor, a pressure sensor, a differential pressure sensor and a flow meter, the pressure drop of the fuel assembly corresponding to different conditions and fragment quantities is monitored online; by monitoring operation of the apparatus in test, it is possible to study the distribution, attachment and blockage of fragments in the fuel assembly and quantitatively evaluate the influence of fragments in the containment after LOCA (loss of coolant accident) of the pressurized water reactor nuclear power plant, and support is provided to ensure reliable execution of safety functionality of an emergency core cooling system of the pressurized water reactor nuclear power plant.

Description

technical field [0001] The invention belongs to the technical field of nuclear safety, and in particular relates to an online monitoring device for the influence of nuclear power plant containment fragments on the pressure drop of fuel assemblies. It can be mainly used to simulate the impact on the pressure drop of the fuel assembly after the containment fragments enter the hypothetical loss of water accident (LOCA) in the PWR nuclear power plant. Background technique [0002] In the recirculation stage (LTCC) of a hypothetical loss of water accident (LOCA) in a PWR nuclear power plant, a large number of debris may be generated in the containment due to the effects of tearing of the breach, injection of high-temperature and high-pressure water, and corrosion or dissolution of materials. These debris, including some impurities, silt, and foreign matter accumulated in the containment, will enter the containment pit due to the migration of the water flow in the containment afte...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 牛风雷卓卫乾郭张鹏王达
Owner NORTH CHINA ELECTRIC POWER UNIV (BAODING)
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