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Volume control method for non-condensable gas at top of pressure vessel

A pressure vessel and volume control technology, applied in the direction of reducing greenhouse gases, climate sustainability, reactors, etc., can solve the problems of inability to discharge the non-condensable gas of the reactor pressure vessel, affect the heat transfer of the reactor core, etc., and achieve beneficial and effective Effects of draining, improving safety, preventing and reducing the probability of core damage

Pending Publication Date: 2021-06-04
CHINA NUCLEAR POWER TECH RES INST CO LTD +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Under accident conditions, the non-condensable gas in the reactor pressure vessel cannot be discharged, which affects the heat transfer of the reactor core

Method used

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  • Volume control method for non-condensable gas at top of pressure vessel
  • Volume control method for non-condensable gas at top of pressure vessel
  • Volume control method for non-condensable gas at top of pressure vessel

Examples

Experimental program
Comparison scheme
Effect test

no. 1 example

[0043] like figure 1 As shown, in the first embodiment of the method for controlling the volume of non-condensable gas at the top of the pressure vessel of the present invention, it can be used in a reactor, including the following steps:

[0044] S1: monitor the operating status of the reactor; when the reactor is in the stage of serious accident prevention function, perform step S2; when the reactor is in the stage of severe accident mitigation function, perform step S3;

[0045] S2: Monitor the real-time water level and / or real-time subcooling degree of the pressure vessel, and start emergency venting at the top of the pile when the real-time water level of the pressure vessel is lower than the first set water level and / or the real-time subcooling degree is greater than the set subcooling degree system;

[0046] S3: Start the stack top emergency exhaust system.

[0047] In this embodiment, the monitoring of the operating state of the reactor is generally divided into a se...

no. 2 example

[0066] On the basis of the first embodiment, combining image 3 , before step S2-3, further includes step S2-4: monitor the real-time subcooling degree of the pressure vessel, and execute step S2-3 when the real-time subcooling degree is greater than the set subcooling degree. That is, the water level is monitored by a thermocouple or a differential pressure gauge, and the subcooling degree is judged at the same time.

[0067] Subcooling degree ΔT of nuclear power plant core outlet coolant sat Monitoring is realized by the core cooling monitoring system. ΔT sat is the saturation temperature T under the absolute pressure of the primary circuit sat and the difference between the core outlet coolant temperature.

[0068] There are three core cooling states:

[0069] ①ΔT sat <-ε: overheating (insufficient cooling);

[0070] ②-εsat ≤ε: saturated (two-phase state cooling);

[0071] ③ΔT sat >ε: supercooled (fully cooled).

[0072] Among them, ε is considering ΔT sat Measur...

no. 3 example

[0079] On the basis of the second embodiment, combining Figure 4 , after step S2-4, also includes step S2-5: monitoring the actual water level L of the pressurizer of the reactor pzr , when the water level of the voltage stabilizer is greater than the preset water level of the voltage stabilizer, step S2-3 is executed.

[0080] Under normal operating conditions of nuclear power plants, changes in the average temperature of the primary circuit will cause changes in the water level of the pressurizer. When the water level in the regulator is too high, the regulator will lose the ability to control the pressure of the primary circuit system, and there is a danger of water entering the safety valve group; if the water level is too low, the resistance heating element of the heater may be exposed to the air Danger. For this reason, this embodiment monitors and adjusts the water level of the voltage stabilizer to keep the water level of the voltage stabilizer within a normal opera...

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Abstract

The invention relates to a volume control method for non-condensable gas at the top of a pressure vessel, the method can be used in a reactor and comprises the following steps of: S1, monitoring the running state of the reactor; when the reactor is in a serious accident prevention function stage, executing S2; when the reactor is in a serious accident relieving functional stage, executing S3; S2, monitoring the real-time water level and / or the real-time supercooling degree of the pressure vessel, and when the real-time water level of the pressure vessel is lower than a first set water level and / or the real-time supercooling degree is larger than a set supercooling degree, starting a reactor top accident exhaust system; and S3, starting the reactor top accident exhaust system. The invention provides a method for controlling and removing non-condensable gas and recovering the water level of a coolant in the pressure vessel, the requirement for water level signal monitoring in the nuclear power plant accident operation regulation is fully considered, the start-stop control condition of the reactor accident exhaust system is reasonably formulated, and the safety of the nuclear power unit is further improved.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor accident mitigation methods, in particular to a method for controlling the volume of non-condensable gas at the top of a pressure vessel. Background technique [0002] In the pressurized water reactor nuclear power unit of the nuclear power plant, the core is built into the pressure vessel. During some accidents (such as beyond design basis accidents, severe accidents, etc.) and after the accident, a large amount of accumulated gas (water vapor and / or non-condensable gas) may be generated in the core, and part of the accumulated gas is accumulated on the top of the pressure vessel. This may have the following adverse effects: [0003] — affect the core heat transfer; [0004] — disruption of the natural circulation of reactor coolant; [0005] - There are two free interfaces in the coolant system, affecting depressurization and refilling of the system. [0006] Primary circuit accident...

Claims

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Application Information

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IPC IPC(8): G21C15/18G21C15/12
CPCG21C15/18G21C15/12Y02E30/30
Inventor 张娟花安云娜林继铭卢向晖赵鑫海陈鹏
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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