WO2018108119A1 - 核电站反应堆放射性废液中气体杂质的脱气装置和方法 - Google Patents

核电站反应堆放射性废液中气体杂质的脱气装置和方法 Download PDF

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WO2018108119A1
WO2018108119A1 PCT/CN2017/116056 CN2017116056W WO2018108119A1 WO 2018108119 A1 WO2018108119 A1 WO 2018108119A1 CN 2017116056 W CN2017116056 W CN 2017116056W WO 2018108119 A1 WO2018108119 A1 WO 2018108119A1
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gas
degassing
tower
waste liquid
water
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PCT/CN2017/116056
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English (en)
French (fr)
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潘跃龙
霍明
兰立君
盛成
杨林君
刘勇
张裕嘉
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深圳中广核工程设计有限公司
中广核工程有限公司
中国广核集团有限公司
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Publication of WO2018108119A1 publication Critical patent/WO2018108119A1/zh

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/02—Treating gases
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing

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  • the invention belongs to the technical field of nuclear power, and more particularly to a degassing device and method for gas impurities in a radioactive waste liquid of a nuclear power plant reactor.
  • a degassing device In order to remove the hydrogen and radioactive fission gases in the primary circuit of the nuclear power plant reactor, so that the primary circuit water quality meets the nuclear power plant operation requirements, a degassing device is required to eliminate the hydrogen and radioactivity in the primary circuit through direct or indirect operation of the degassing device during operation. Fission gas, thereby reducing its content to meet nuclear power plant operating requirements.
  • a positive degassing device can achieve a certain degassing effect, but has the following disadvantages: during the starting process, a large amount of nitrogen is required to purify the device and the pipeline to reduce the oxygen concentration in the device, so A large amount of control logic and supporting equipment need to be added to complete the degassing process; the startup process is complicated, the system failure rate is high, and the system availability is reduced; the operator needs to intervene in a large amount of process, and the degree of automation is low; Degassing, in order to achieve the saturation state of the coolant, in the process of degassing, it also needs to consume a large amount of heat to saturate the coolant, and the evaporated coolant also needs to be cooled by the heat exchanger for air cooling and condensing and refluxing; It is necessary to consider the anti-hydrogen explosion measures, and additional devices such as hydrogen concentration measuring instruments are needed to measure the hydrogen concentration of the plant and all valves and instrument parts.
  • the degassing device using vacuum pump negative pressure is simpler than the positive pressure degassing device, but it also has some defects: during the operation of the degassing device, in order to ensure the hydrogen in the device under any working conditions (including leakage)
  • the gas concentration is lower than the explosion limit, and it is necessary to ensure that a large amount of nitrogen is purged to the degassing device at this time.
  • a large amount of carrier gas is required to cooperate with the relevant process operation;
  • the large amount of nitrogen added increases the flow rate of the vacuum pump, thereby increasing the volume of the overall vacuum unit; increasing the potential gas effluent discharge from the nuclear power plant.
  • the object of the present invention is to provide an energy-saving, efficient and safe degassing device and method for gas impurities in a radioactive waste liquid of a nuclear power plant reactor.
  • the present invention provides a degassing device for gas impurities in a radioactive waste liquid of a nuclear power plant reactor, which comprises:
  • a degassing tower for receiving the radioactive waste liquid of the nuclear power plant reactor and removing the dissolved gas in the waste liquid, the degassing tower having an overhead gas outlet and a tower liquid outlet;
  • a condenser connected to the degassing tower and located downstream thereof for condensing the gas collected at the top of the degassing tower;
  • a vacuum pump in communication with the condenser for extracting and compressing the gas condensed by the condenser and the uncondensed water vapor to maintain the required operating pressure within the column;
  • a gas water separator connected to the vacuum pump for separating gas and water and removing the gas.
  • the gaseous impurities in the waste liquid include hydrogen gas and/or radioactive gas.
  • the gas water separator includes a gas outlet at the top and a water outlet at the bottom.
  • the water outlet communicates with the condensate discharge pump to discharge the separated condensed water to the downstream processing system.
  • a sealed water cooler is disposed between the condensate drain pump and the vacuum pump for heat exchange of the condensed water after degassing.
  • the sealed water cooler comprises a sealed water outlet and a sealed water inlet, and the sealed water outlet is connected with the vacuum pump to heat exchange The sealed water is supplied to the vacuum pump.
  • the degassing device as a gas impurity in the radioactive waste liquid of the nuclear power plant reactor of the present invention
  • the degassing device further comprising a coolant transfer pump connected to the degassing tower and located downstream thereof for conveying The gas tower tower removes the coolant from the gaseous impurities.
  • the degassing device further comprising communicating with the degassing tower and connecting the coolant transfer pump to a pipeline A coolant circulation pump for conveying the circulating liquid required for heat exchange for the degassing tower.
  • an electric heater is arranged between the coolant circulation pump and the degassing tower for cooling to the degassing tower The agent is heated to obtain the heat required for evaporation of the liquid entering the degassing tower.
  • the present invention also provides a method for degassing gaseous impurities in a radioactive waste liquid of a nuclear power plant reactor, which comprises the following steps:
  • the pressure of the control tower is 7 kPa to 13.5 kPa, and the temperature is 39 ° C. 51.8 ° C.
  • the condensed water is further sent to the sealed water cooler for heat exchange through the condensate discharge pump.
  • the degassing method further comprises conveying the sealed water after the heat exchange to a vacuum pump, and the pressure of the sealed water entering the vacuum pump is lower than the suction of the vacuum pump Working pressure at the mouth.
  • the method further comprises: transferring the tower coolant to the electric heater through a circulation pump, and then sending the degassing Inside the tower.
  • the degassing device and method for gas impurities in the radioactive waste liquid of the nuclear power plant reactor of the present invention have the following advantages: (1) reducing the amount of carrier gas used, and reducing the emission of radioactive gas for the nuclear power plant; (2) only need to add a small amount of heat in the degassing process to make the waste liquid saturated, saving the energy required for the waste liquid to reach saturation; (3) blowing nitrogen on the device and pipeline without using nitrogen Sweep, saving nitrogen emissions; (4) using a negative pressure degassing process, using the conventional equipment liquid ring vacuum pump to provide the vacuum required by the system to complete the degassing process, saving construction costs; (5) this The invention has simple process, convenient operation, high degree of automation and safe degassing, and can ensure system safety when the system leaks and breaks.
  • FIG. 1 is a schematic view of a degassing device for gas impurities in a radioactive waste liquid of a nuclear power plant reactor of the present invention.
  • the degassing device for gas impurities in the radioactive waste liquid of the nuclear power plant reactor of the present invention comprises: a degassing tower 10, a condenser 20 connected to the top of the degassing tower 10, and a condenser 20 outlet.
  • a vacuum pump 30 is disposed on the pipeline, and a gas water separator 40 in communication with the outlet line of the vacuum pump 30.
  • the degassing tower 10 is configured to receive the radioactive waste liquid of the nuclear power plant reactor and remove the dissolved gas in the waste liquid, the degassing tower 10 is a packed tower, the liquid distributor (not shown) is arranged in the tower, and the display tower is installed on the tower.
  • a pressure gauge (not shown) and a temperature sensor (not shown) for displaying the temperature of the column, the degassing column 10 has an overhead gas outlet 102, a column liquid outlet 104, a radioactive waste liquid inlet 106, and a condenser reflux.
  • the condensate inlet 108 and the circulating coolant inlet 110 of the column kettle are examples of the degassing tower 10 a packed tower, the liquid distributor (not shown) is arranged in the tower, and the display tower is installed on the tower.
  • the degassing column 10 has an overhead gas outlet 102, a column liquid outlet 104,
  • the pressure of the degassing column 10 is controlled to be 12.5 kPa and the temperature is 50 ° C; the radioactive waste liquid enters the liquid distributor in the degassing column 10 and enters the packing in the column, and the rising steam is in the packing.
  • gas-liquid mass transfer is carried out during the contact process, and the gas dissolved in the waste liquid, such as hydrogen gas and radioactive gas, is carried away by steam and sent upward to the top of the tower, thereby realizing the degassing process of the waste liquid.
  • the condenser 20 is a water-cooled condenser, and the condensed gas is condensed by using chilled water as a cooling medium.
  • the uncondensed gas is withdrawn from the condenser outlet 206, and the condensed condensate is dissolved due to dissolution.
  • the gas is returned to the top of the degassing tower and degassing is continued.
  • the temperature of the reflux condensate is controlled at the boiling temperature of the liquid in the degassing tower to prevent the precipitated gas from being dissolved again in the liquid, and finally the hydrogen in the radioactive waste liquid.
  • the radioactive gas is continuously removed and the amount of steam that is not condensed after passing through the condenser 20 is controlled to prevent hydrogen explosion.
  • the vacuum pump 30 is a liquid ring vacuum pump, and one end is connected to the condenser outlet 206 through a pipe for supplying power, extracting and compressing the gas condensed by the condenser 20 and the uncondensed water vapor to maintain the required inside the tower.
  • the operating pressure, the uncondensed steam coming out of the condenser 20 is sent to the gas water separator 40 for separation after being compressed and condensed by the vacuum pump 30, and the uncondensed steam also helps the vacuum pump 30 to improve the pumping capacity; the vacuum pump inlet 302
  • a gas sampling port (not shown) is disposed on the pipeline at the front end for detecting the concentration of hydrogen entering the vacuum pump 30.
  • a flow regulating valve (not shown) is further disposed on the front end of the vacuum pump inlet 302 for controlling the entry into the vacuum pump 30.
  • the concentration of hydrogen in the mixed gas into the vacuum pump 30, the volume concentration of hydrogen is below the explosion limit, thereby achieving the purpose of hydrogen explosion-proof control.
  • the gas-water separator 40 is in communication with an outlet line of the vacuum pump 30 for separating the gas and water compressed by the vacuum pump 30.
  • the gas-water separator 40 is provided with a gas outlet 406 at the top and a water outlet 404 at the bottom, and the non-condensing after separation
  • the gas such as hydrogen and radioactive gas, is discharged from the gas outlet 406 for post-treatment, and the separated water is sent to the subsequent section through the water outlet 404 at the bottom for processing, and finally the degassing process of the entire degassing device is realized.
  • a condensate drain pump 50 is provided on the water outlet 404 line at the bottom of the gas water separator 40 for powering the discharge of the condensed water while providing power for the heat exchange of the condensed water.
  • the condensate discharge pump 50 is in communication with the vacuum pump 30 to supply the condensed water separated by the gas-water separator 40 to the vacuum pump 30 for repeated use.
  • a sealed water cooler 60 is provided downstream of the condensate drain pump outlet to cool the separated water, and the sealed water cooler 60 provides cooling source using equipment cooling water.
  • a coolant transfer pump 70 is disposed downstream of the degassing tower column outlet 104 line for conveying the tower block coolant after the degassing column 10 is separated.
  • One end of the circulation pump 80 is connected to the degassing tower column outlet 104 through a pipe, and the other end is connected to the circulating coolant inlet 110 on the degassing column 10 through a pipe for conveying the circulating liquid required for heat exchange for the degassing column 10.
  • An electric heater 90 is disposed on the line between the circulation pump 80 and the degassing column 10 for heating the coolant delivered to the degassing column 10 to obtain the liquid required for evaporation into the degassing column 10. Heat.
  • the process of degassing gas impurities in the radioactive waste liquid of the nuclear power plant reactor of the present invention is as follows:
  • the condenser 20 After each device is connected by a pipe, after measuring the insulation of the motor, the condenser 20 is turned on, and the condenser 20 is put into use.
  • a certain amount of water containing no hydrogen and radioactive gas is input to the degassing tower 10 through a pipeline.
  • the circulation pump 80 is started to circulate, and then the electric heater 90 is started.
  • the heating temperature of the electric heater 90 is adjusted to heat the circulating liquid, and the vacuum pump 30 is started to perform the pumping, and the gas-water separator 40 is put into use.
  • the radioactive waste liquid is input to the degassing tower 10, and the coolant transfer pump 70 is started to transport the tower coolant, and the outlet flow rate of the coolant transfer pump 70 is controlled during the transportation to maintain the liquid level of the tower.
  • the pressure of the column of the degassing tower 10 is gradually adjusted to 12.5 kPa by the vacuum pump 30, and the temperature of the degassing column 10 is 50 ° C.
  • the steam of the radioactive waste liquid rising through the tower is substantially completely boiled after being exchanged in the packing, and the waste liquid is in the waste liquid.
  • Most of the dissolved gas is resolved, and the analyzed gas enters the condenser 20 from the top outlet 102 of the degassing tower.
  • the temperature of the chilled water of the condenser 20 is adjusted to control the reflux to the degassing.
  • the temperature of the condensate in the column 10 is the boiling point temperature of the liquid in the degassing column 10 to prevent the precipitated gas from being dissolved again in the liquid; and periodically passing through the gas sampling port on the line at the front end of the condenser inlet 202 (not shown) Sampling, detecting the concentration of hydrogen in the degassing column 10, and ensuring that the hydrogen concentration in the degassing column 10 is below the explosion limit by adjusting the operating power of each device.
  • the gas from the condenser 20 is compressed by the vacuum pump 30, and the compressed gas-liquid mixture is sent to the gas-water separator 40 for gas-liquid separation, and the non-condensable gas is discharged through the gas outlet line of the gas-water separator 40 for treatment.
  • the condensate discharge pump 50 is turned on, the condensed water in the gas water separator is discharged and transported, the outlet flow rate of the condensate discharge pump 50 is controlled, and the liquid level of the gas water separator is maintained. .
  • the sealed water cooler 60 is put into use, the temperature of the cold source of the sealed water cooler 60 is adjusted, and the pressure of the sealed water entering the vacuum pump 30 is controlled to be lower than the working pressure of the suction end of the vacuum pump 30; the gas sampling at the front end of the vacuum pump inlet 302 is periodically timed.
  • a port (not shown) is sampled to detect the concentration of hydrogen entering the vacuum pump while controlling the concentration of hydrogen entering the vacuum pump through a flow regulating valve (not shown) on the forward line of the vacuum pump inlet 302 to allow mixing into the vacuum pump 30.
  • the volume concentration of hydrogen is below the explosion limit, thus achieving the purpose of hydrogen explosion-proof control.
  • the degassing device for the gas impurities in the radioactive waste liquid of the nuclear power plant reactor can not only remove hydrogen and radioactive gas in the radioactive waste liquid of the nuclear power plant reactor, but also can be used for degassing the general liquid, such as removal. Oxygen, nitrogen and other gases have a wide range of practicalities.
  • the degassing apparatus and method for gas impurities in the radioactive waste liquid of the nuclear power plant reactor of the present invention have the following advantages: (1) reducing the amount of carrier gas used For nuclear power plants, the emission of radioactive gas is reduced; (2) only a small amount of heat needs to be added during the degassing process to make the waste liquid saturated, saving the energy required for the waste liquid to reach saturation; 3) No need to use nitrogen to purge the device and pipeline, saving nitrogen emissions; (4) Using a negative pressure degassing process, using the conventional equipment liquid ring vacuum pump to provide the required vacuum of the system can be completed The gas process saves the construction cost; (5)
  • the invention has the advantages of simple process, convenient operation, high degree of automation, and safe degassing, and the system can be ensured when the system leaks and breaks.

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Abstract

一种核电站反应堆放射性废液中气体杂质的脱气装置，其包括：脱气塔（10），用于接收核电站反应堆放射性废液并脱除废液中溶解的气体，脱气塔（10）具有塔顶气体出口（102）和塔釜液体出口（104）；与脱气塔（10）相连通且位于其下游的冷凝器（20），用于对脱气塔（10）塔顶采出的气体进行冷凝；与冷凝器（20）相连通的真空泵（30），用于抽出并压缩经过冷凝器（20）冷凝后的气体和未冷凝的水蒸汽，以维持塔内所需的运行压力；以及与真空泵（30）相连通的气水分离器（40），用于分离气体和水，将气体除去。此外，还包括一种核电站反应堆放射性废液中气体杂质的脱气方法。该核电站反应堆放射性废液中气体杂质的脱气装置和方法采用负压脱气，操作方便，安全可靠，即使系统出现泄漏时也能保证系统安全。

Description

核电站反应堆放射性废液中气体杂质的脱气装置和方法 技术领域
本发明属于核电技术领域，更具体地说，本发明涉及一种核电站反应堆放射性废液中气体杂质的脱气装置和方法。
背景技术
核电站反应堆放射性废液中存在着由生产运行产生的氢气和多种放射性气体，放射性废液中的气体大都有害：氢气是易燃易爆的气体，当氢气浓度超标时，存在爆炸风险，放射性气体会对人体和环境造成损害。因此，有必要对反应堆放射性废液中存在的气体杂质进行脱除。
为了脱除核电站反应堆一回路中的氢气和放射性裂变气体，使一回路水质满足核电站运行要求，需要设置脱气装置，通过脱气装置在运行期间的直接或者间接运行，排除一回路中氢气和放射性裂变气体，从而降低其含量以满足核电站运行要求。
现有核电技术中，采用正压的脱气装置能达到一定的脱气效果，但存在以下缺点：在启动过程中，需要大量氮气对装置和管道进行吹扫以降低装置内的氧气浓度，因此，需增加大量的控制逻辑和配套设备用以配合完成脱气过程；启动过程复杂，系统故障率较高，降低系统的可用性；操作员需要干预的过程量多，自动化程度低；由于是正压脱气，为了达到冷却剂的饱和状态，在脱气过程中，还需要消耗大量的热量使冷却剂达到饱和状态，蒸发的冷却剂也需要换热器冷却进行气冷和冷凝回流；此外，还需考虑防氢爆措施，需额外的增设氢气浓度测量仪表等装置，用以测量厂房和所有阀门以及仪表部分的氢气浓度。
采用真空泵负压的脱气装置虽然工艺较正压脱气装置简单，但也存在一些缺陷：在脱气装置运行期间，为了保证装置在任何工况下(包括泄漏)装置里的氢 气浓度低于爆炸极限，需要时刻保证有大量的氮气对脱气装置进行吹扫，此时，除了配备相关气体管线外，还需有配置大量的载气用以配合相关工艺操作；装置内通入的大量氮气增加了真空泵的流量，从而增加了整体真空单元的体积；增加了核电站潜在的气体流出物排放量。
有鉴于此，确有必要提供一种节能、高效、安全的核电站反应堆放射性废液中气体杂质的脱气装置和方法。
发明内容
本发明的目的在于：提供一种节能、高效、安全的核电站反应堆放射性废液中气体杂质的脱气装置和方法。
为了实现上述发明目的，本发明提供了一种核电站反应堆放射性废液中气体杂质的脱气装置，其包括：
脱气塔，用于接收核电站反应堆放射性废液并脱除废液中溶解的气体，脱气塔具有塔顶气体出口和塔釜液体出口；
与脱气塔相连通且位于其下游的冷凝器，用于对脱气塔塔顶采出的气体进行冷凝；
与冷凝器相连通的真空泵，用于抽出并压缩经过冷凝器冷凝后的气体和未冷凝的水蒸汽，以维持塔内所需的运行压力；以及
与真空泵相连通的气水分离器，用于分离气体和水，将气体除去。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进，所述废液中的气体杂质包括氢气和/或放射性气体。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进，所述气水分离器包括顶部的气体出口和底部的水出口。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进，所述水出口与冷凝液排放泵相连通以将分离出的冷凝水排放到下游处理系统。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进， 所述冷凝液排放泵与所述真空泵之间设有一密封水冷却器，用于为脱气后的冷凝水换热。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进，所述密封水冷却器包括一密封水出口和一密封水入口，密封水出口与真空泵相连通以将换热后的密封水供应给真空泵。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进，所述脱气装置还包括与所述脱气塔相连通且位于其下游的一冷却剂输送泵，用于输送脱气塔塔釜的脱除了气体杂质的冷却剂。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进，所述脱气装置还包括与所述脱气塔相连通且与所述冷却剂输送泵连接在一根管线上的冷却剂循环泵，用于为脱气塔输送换热所需的循环液体。
作为本发明核电站反应堆放射性废液中气体杂质的脱气装置的一种改进，所述冷却剂循环泵与所述脱气塔之间设有电加热器，用来为输送到脱气塔的冷却剂进行加热，使进入到脱气塔内的液体获得蒸发所需的热量。
为了实现上述发明目的，本发明还提供了一种核电站反应堆放射性废液中气体杂质的脱气方法，其包括以下步骤：
1)将核电站反应堆放射性废液输送入脱气塔进行解析分离，放射性废液在填料中换热后实现气液分离；
2)用冷凝器对从脱气塔塔顶采出的气体进行冷却，经冷凝器冷凝下来的液体回流到脱气塔内，继续进行脱气；
3)使用真空泵对冷凝器和脱气塔抽气，并对从冷凝器出口出来的气体进行压缩；
4)将真空泵输出的气水混合物送入气水分离器进行分离；
5)将气水分离器顶部的不凝性气体从顶部排气口送往下游系统处理，气水分离器冷凝下来的冷凝水通过冷凝液排放泵送到下游系统处理；以及
6)将脱气塔脱气后的塔釜冷却剂通过塔釜冷却剂输送泵输送到下游系统处理。
作为本发明核电站反应堆放射性废液中气体杂质的脱气方法的一种改进，所述步骤1)中，脱气塔进行脱气时，控制塔釜压力为7kPa～13.5kPa，温度为39℃～51.8℃。
作为本发明核电站反应堆放射性废液中气体杂质的脱气方法的一种改进，在所述步骤5)后还包括将所述冷凝水通过冷凝液排放泵送入密封水冷却器换热。
作为本发明核电站反应堆放射性废液中气体杂质的脱气方法的一种改进，所述脱气方法还包括将所述换热后的密封水输送至真空泵，密封水进入真空泵的压力低于真空泵吸入口端的工作压力。
作为本发明核电站反应堆放射性废液中气体杂质的脱气方法的一种改进，在所述步骤6)后还包括将所述塔釜冷却剂通过循环泵输送到电加热器加热后送入脱气塔内。
与现有技术相比，本发明核电站反应堆放射性废液中气体杂质的脱气装置和方法具有以下优点：(1)减小了载气的使用量，对于核电站而言，减少了放射性气体的排放量；(2)在脱气过程中仅需补充少量的热量就能使废液达到饱和状态，节省了废液达到饱和状态所需要的能量；(3)不需要使用氮气对装置和管道进行吹扫，节省了氮气的排放量；(4)采用负压脱气工艺，使用常规配套设备液环真空泵来提供系统所需的真空度就可以完成脱气过程，节省了建设成本；(5)本发明工艺简单，操作方便，自动化程度高，脱气安全，当系统出现泄漏破口时，仍能保证系统安全。
附图说明
下面结合附图和具体实施方式，对本发明核电站反应堆放射性废液中气体杂质的脱气装置和方法进行详细说明，其中：
图1为本发明核电站反应堆放射性废液中气体杂质的脱气装置的示意图。
具体实施方式
为了使本发明的发明目的、技术方案及其有益技术效果更加清晰，以下结合附图和具体实施方式，对本发明进行进一步详细说明。应当理解的是，本说明书中描述的具体实施方式仅仅是为了解释本发明，并非为了限定本发明。
请参阅图1所示，本发明核电站反应堆放射性废液中气体杂质的脱气装置包括：脱气塔10，与脱气塔10塔顶采出管线连接的冷凝器20，其中，冷凝器20出口管线上设有真空泵30，以及与真空泵30出口管线连通的气水分离器40。
脱气塔10用于接收核电站反应堆放射性废液并脱除废液中溶解的气体，脱气塔10为填料塔，塔内设有液体分布器(未图示)，塔上安装有显示塔釜压力的压力表(未图示)和显示塔釜温度的温度传感器(未图示)，脱气塔10具有塔顶气体出口102、塔釜液体出口104、放射性废液进入口106、冷凝器回流冷凝液入口108以及塔釜的循环冷却剂入口110。在图示实施方式中，控制脱气塔10的压力为12.5kPa，温度为50℃；放射性废液进入脱气塔10内的液体分布器后进入塔内的填料，与上升的蒸汽在填料中相遇，在接触过程中进行气液传质，通过蒸汽将溶解于废液中的气体，如氢气和放射性气体带走并向上传送至塔顶，从而实现废液的脱气过程。
冷凝器20为水冷式冷凝器，用冷冻水作为冷介质对塔顶采出气体进行冷凝，在图示实施方式中，未凝气体从冷凝器出口206抽出，冷凝下来的冷凝液由于溶解有残余的气体重新回流到脱气塔顶部，继续进行脱气，回流冷凝液的温度控制在脱气塔内液体的沸点温度，以防止析出的气体再次溶解在液体中，最终使放射性废液中的氢气和放射性气体不断的脱除，并控制经过冷凝器20后未冷凝的蒸汽量防止氢气爆炸。
真空泵30为液环真空泵，一端通过管道连接冷凝器出口206，用于提供动力，抽出并压缩经过冷凝器20冷凝后的气体和未冷凝的水蒸汽，维持塔内所需 的运行压力，从冷凝器20出来的未冷凝的蒸汽在真空泵30压缩冷凝冷凝后被送至气水分离器40进行分离，未冷凝的蒸汽还有助于真空泵30提高抽气能力；真空泵入口302前端的管线上设有气体取样口(未图示)，用来检测进入真空泵30中氢气的浓度，真空泵入口302前端管线上还设置有流量调节阀(未图示)，用来控制进入真空泵30中氢气的浓度，使进入真空泵30的混合气体中，氢气的体积浓度在爆炸极限之下，从而达到氢气防爆控制目的。
气水分离器40与真空泵30出口管线相连通，用于分离经过真空泵30压缩后的气体和水，气水分离器40设有顶部的气体出口406和底部的水出口404，分离后的不凝气体，如氢气及放射性气体从气体出口406排出进行后处理，分离后的水通过底部的水出口404送入后续工段进行处理，最终实现整个脱气装置的脱气过程。
气水分离器40底部的水出口404管线上设有冷凝液排放泵50，用于为冷凝水的排放提供动力，同时为冷凝水的换热提供动力。
冷凝液排放泵50与真空泵30相连通，以将气水分离器40分离出的冷凝水供应给真空泵30重复使用。根据本发明的一个优选实施方式，在冷凝液排放泵出口的下游设置一个密封水冷却器60，以冷却被分离出的水，密封水冷却器60采用设备冷却水提供冷源。
脱气塔塔釜出口104管线下游设有冷却剂输送泵70，用于输送脱气塔10分离后的塔釜冷却剂。
循环泵80一端通过管道连接脱气塔塔釜出口104，另一端通过管道连接脱气塔10上的循环冷却剂入口110，用于为脱气塔10输送换热所需的循环液体。
电加热器90设置在循环泵80与脱气塔10之间的管线上，用来为输送到脱气塔10的冷却剂进行加热，使进入到脱气塔10内的液体获得蒸发所需的热量。
请继续参阅图1所示，本发明核电站反应堆放射性废液中气体杂质的脱气方法过程如下：
各个装置通过管道连接好后，测量电机绝缘合格后，开启冷凝器20冷冻水，将冷凝器20投入使用。
通过管线对脱气塔10输入一定量的不含氢气和放射性气体的水，待脱气塔10内塔釜的液体达到一定液位后，启动循环泵80进行循环，然后启动电加热器90，调节电加热器90的加热温度对循环液进行加热，并启动真空泵30进行抽气，同时将气水分离器40投入使用。
对脱气塔10输入放射性废液，并启动冷却剂输送泵70对塔釜冷却剂进行输送，输送过程中控制冷却剂输送泵70的出口流量，维持塔釜液位。
通过真空泵30逐渐调节脱气塔10的塔釜压力到12.5kPa，脱气塔10的温度到50℃，放射性废液经塔釜上升的蒸汽在填料中热交换后基本能够全部沸腾，废液中溶解的气体大部分解析出来，解析出来的气体从脱气塔塔顶出口102进入冷凝器20，待脱气塔10压力和温度稳定后，调节冷凝器20冷冻水的温度，控制回流到脱气塔10内的冷凝液的温度为脱气塔10内液体的沸点温度，以防止析出的气体再次溶解在液体中；并定时通过冷凝器入口202前端的管线上的气体取样口(未图示)取样，检测脱气塔10内的氢气浓度，通过调节各装置的运行功率保证脱气塔10内的氢气浓度在爆炸极限以下。
从冷凝器20出来的气体通过真空泵30进行压缩，压缩后的气液混合物送入气水分离器40进行气液分离，不凝气体通过气水分离器40气体出口管线排出进行处理，当气水分离器40底部的冷凝水达到一定液位后，开启冷凝液排放泵50，排放和输送气水分离器中的冷凝水，控制冷凝液排放泵50的出口流量，维持气水分离器的液位。将密封水冷却器60投入使用，调节密封水冷却器60冷源的温度，并控制密封水进入真空泵30的压力低于真空泵30吸入口端的工作压力；定时通过真空泵入口302前端管线上的气体取样口(未图示)取样，用来检测进入真空泵中氢气的浓度，同时通过真空泵入口302前端管线上的流量调节阀(未图示)来控制进入真空泵中氢气的浓度，使进入真空泵30的混合气体中， 氢气的体积浓度在爆炸极限之下，从而达到氢气防爆控制目的。
需要说明的是，本发明核电站反应堆放射性废液中气体杂质的脱气装置不仅可脱除核电站反应堆放射性废液中的氢气和放射性气体，而且还可以用来对一般液体的脱气，如脱除氧气、氮气等其他气体，具有广泛的实用性。
结合以上对本发明实施方式的详细描述可以看出，相对于现有技术，本发明核电站反应堆放射性废液中气体杂质的脱气装置和方法具有以下优点：(1)减小了载气的使用量，对于核电站而言，减少了放射性气体的排放量；(2)在脱气过程中仅需补充少量的热量就能使废液达到饱和状态，节省了废液达到饱和状态所需要的能量；(3)不需要使用氮气对装置和管道进行吹扫，节省了氮气的排放量；(4)采用负压脱气工艺，使用常规配套设备液环真空泵来提供系统所需的真空度就可以完成脱气过程，节省了建设成本；(5)本发明工艺简单，操作方便，自动化程度高，脱气安全，当系统出现泄漏破口时，仍能保证系统安全。
根据上述说明书的揭示和教导，本发明所属领域的技术人员还可以对上述实施方式进行适当的变更和修改。因此，本发明并不局限于上面揭示和描述的具体实施方式，对本发明的一些修改和变更也应当落入本发明的权利要求的保护范围内。此外，尽管本说明书中使用了一些特定的术语，但这些术语只是为了方便说明，并不对本发明构成任何限制。

Claims (14)

  1. 一种核电站反应堆放射性废液中气体杂质的脱气装置，其特征在于，包括：
    脱气塔，用于接收核电站反应堆放射性废液并脱除废液中溶解的气体，脱气塔具有塔顶气体出口和塔釜液体出口；
    与脱气塔相连通且位于其下游的冷凝器，用于对脱气塔塔顶采出的气体进行冷凝；
    与冷凝器相连通的真空泵，用于抽出并压缩经过冷凝器冷凝后的气体和未冷凝的水蒸汽，以维持塔内所需的运行压力；以及
    与真空泵相连通的气水分离器，用于分离气体和水，将气体除去。
  2. 根据权利要求1所述的脱气装置，其特征在于，所述废液中的气体杂质包括氢气和/或放射性气体。
  3. 根据权利要求1所述的脱气装置，其特征在于，所述气水分离器包括顶部的气体出口和底部的水出口。
  4. 根据权利要求3所述的脱气装置，其特征在于，所述水出口与冷凝液排放泵相连通以将分离出的冷凝水排放到下游处理系统。
  5. 根据权利要求4所述的脱气装置，其特征在于，所述冷凝液排放泵与所述真空泵之间设有一密封水冷却器，用于为脱气后的冷凝水换热。
  6. 根据权利要求5所述的脱气装置，其特征在于，所述密封水冷却器包括一密封水出口和一密封水入口，密封水出口与真空泵相连通以将换热后的密封水供应给真空泵。
  7. 根据权利要求1所述的脱气装置，其特征在于，还包括与所述脱气塔相连通且位于其下游的一冷却剂输送泵，用于输送脱气塔塔釜的脱除了气体杂质的冷却剂。
  8. 根据权利要求1所述的脱气装置，其特征在于，还包括与所述脱气塔相 连通且与所述冷却剂输送泵连接在一根管线上的冷却剂循环泵，用于为脱气塔输送换热所需的循环液体。
  9. 根据权利要求8所述的脱气装置，其特征在于，所述冷却剂循环泵与所述脱气塔之间设有电加热器，用来为输送到脱气塔的冷却剂进行加热，使进入到脱气塔内的液体获得蒸发所需的热量。
  10. 一种核电站反应堆放射性废液中气体杂质的脱气方法，其特征在于，包括以下步骤：
    1)将核电站反应堆放射性废液输送入脱气塔进行解析分离，放射性废液在填料中换热后实现气液分离；
    2)用冷凝器对从脱气塔塔顶采出的气体进行冷却，经冷凝器冷凝下来的液体回流到脱气塔内，继续进行脱气；
    3)使用真空泵对冷凝器和脱气塔抽气，并对从冷凝器出口出来的气体进行压缩；
    4)将真空泵输出的气水混合物送入气水分离器进行分离；
    5)将气水分离器顶部的不凝性气体从顶部排气口送往下游系统处理，气水分离器冷凝下来的冷凝水通过冷凝液排放泵送到下游系统处理；以及
    6)将脱气塔脱气后的塔釜冷却剂通过塔釜冷却剂输送泵输送到下游系统处理。
  11. 根据权利要求10所述的脱气方法，其特征在于，所述步骤1)中，脱气塔进行脱气时，控制塔釜压力为7kPa～13.5kPa，温度为39℃～51.8℃。
  12. 根据权利要求10所述的脱气方法，其特征在于，在所述步骤5)后还包括将所述冷凝水通过冷凝液排放泵送入密封水冷却器换热。
  13. 根据权利要求10所述的脱气方法，其特征在于，还包括将所述换热后的密封水输送至真空泵，密封水进入真空泵的压力低于真空泵吸入口端的工作压力。
  14. 根据权利要求10所述的脱气方法，其特征在于，在所述步骤6)后还包括将所述塔釜冷却剂通过循环泵输送到电加热器加热后送入脱气塔内。
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