Nuclear power plant volume control box deoxidization testing system and method

A technology for nuclear power plants and monitoring systems, applied in the field of nuclear power, can solve the problems of taking up overhaul time, unable to adjust the deoxidation strategy, unable to pass the purge at one time, etc., and achieve the effect of excellent data support

Active Publication Date: 2019-05-10
SUZHOU NUCLEAR POWER RES INST +3
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  • Abstract
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  • Claims
  • Application Information

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Problems solved by technology

[0018] At present, there are the following problems in the actual operation of the nuclear power plant using the volume control box to deoxygenate the primary circuit: the current method does not have the relevant method for the deoxygenation performance test of the volume control box, and the deoxygenation ope

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  • Nuclear power plant volume control box deoxidization testing system and method
  • Nuclear power plant volume control box deoxidization testing system and method
  • Nuclear power plant volume control box deoxidization testing system and method

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Embodiment Construction

[0063] In order to facilitate the understanding of the present invention, the present invention will be described more fully below with reference to the associated drawings. Typical embodiments of the invention are shown in the drawings. However, the present invention can be embodied in many different forms and is not limited to the embodiments described herein. Rather, these embodiments are provided so that the disclosure of the present invention will be thorough and complete. It should be understood that the embodiments of the present invention and the specific features in the embodiments are detailed descriptions of the technical solutions of the present application, rather than limitations on the technical solutions of the present application. In the case of no conflict, the embodiments of the present invention and the technical features in the embodiments can be combined with each other.

[0064] It should be noted that terms such as "connection" or "connection" mention...

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Abstract

The invention discloses a nuclear power plant volume control box deoxidization testing system and method. The nuclear power plant volume control box deoxidization testing system comprises a top charging and bottom discharging system, a purging system, an oxygen content adjusting system, a temperature control system and a parameter monitoring system. The nuclear power plant volume control box deoxidization testing system provides functions of upper charging and bottom discharging flow control, temperature adjustment, oxygen content control, nitrogen supply, gas discharging and the like, and based on the functions, achieves a testing mode with intermittent purging and pressured air exhausting. The invention also designs corresponding testing methods for different working conditions and helpsacquire rules of influence of volume control box liquid level, waiting time and purging time on intermittent purging deoxidization effects as well as the rules of influence of standing time on pressurized air exhausting deoxidization effects; by comparing the testing data of two methods, difference of intermittent purging and pressured air exhausting in deoxidization effects can be acquired to provided optimized data support for optimization and adjustment of deoxidization strategies of actual generator units.

Description

technical field [0001] The invention relates to the field of nuclear power, in particular to a test system and method for deoxygenating a capacity control box of a nuclear power plant. Background technique [0002] As one of the nuclear auxiliary systems of PWR nuclear power units, the chemical and volume control system plays an important role in the operation; the volume control function compensates the zero power start-up process of the nuclear power plant from the cold state to the hot state or from the zero power to the hot state. The change in coolant circuit water volume caused by the cold shutdown process. figure 1 It is the control schematic diagram of the primary loop chemical capacity system. In order to maintain a constant water level in the coolant circuit, a chemical capacity system connected to the coolant circuit is provided during normal power generation. The chemical capacity system includes a capacity control box, etc. The pipes and equipment in the coolan...

Claims

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Application Information

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IPC IPC(8): G21C17/022G21C17/032C02F1/20
CPCY02E30/30
Inventor 许俊俊洪益群张钊吴天华杨自军何继强圣国龙王树强孙开宝谭世杰沈荣发李明钢张捷沙洪伟李广锋
Owner SUZHOU NUCLEAR POWER RES INST
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