WO2022016869A1 - 一种高温气冷堆核电站冷试期间一回路舱室加热系统及方法 - Google Patents

一种高温气冷堆核电站冷试期间一回路舱室加热系统及方法 Download PDF

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WO2022016869A1
WO2022016869A1 PCT/CN2021/078749 CN2021078749W WO2022016869A1 WO 2022016869 A1 WO2022016869 A1 WO 2022016869A1 CN 2021078749 W CN2021078749 W CN 2021078749W WO 2022016869 A1 WO2022016869 A1 WO 2022016869A1
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cabin
steam generator
pressure vessel
compartment
air
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English (en)
French (fr)
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刘俊峰
武方杰
刘锋
李康
马晓珑
赵博
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Xian Thermal Power Research Institute Co Ltd
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Xian Thermal Power Research Institute Co Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/006—Details of nuclear power plant primary side of steam generators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention belongs to the technical field of nuclear power, and relates to a primary-circuit cabin heating system and method during a cold test of a high-temperature gas-cooled reactor nuclear power plant.
  • the cold test of a nuclear power plant is a joint debugging and verification of the key equipment performance and installation process quality of the nuclear island after the nuclear power plant completes civil construction, equipment installation and single-system commissioning.
  • the purpose is to evaluate the nuclear safety protection by verifying the tightness and strength of the primary loop system. barrier integrity, and obtain initial operational data for primary loop systems and equipment.
  • the primary circuit pressure vessel is the main body of the primary circuit pressure boundary, and its strength and sealing performance are very important to ensure the safe operation of the reactor. According to the requirements of nuclear safety regulations, the strength and sealing performance test of the primary circuit pressure boundary shall be carried out during the cold test.
  • the pre-service pressure test of the primary circuit system is the main test content of the cold test of the nuclear power plant.
  • the primary circuit of the high temperature gas-cooled reactor uses helium as the coolant, which adopts the method of air pressure test.
  • ASME-III-I-NB-6000 For the system pressure test before the reactor pressure vessel is charged, the test temperature should not be lower than RT NDT +33°C, where RT NDT is the main material of the pressure vessel.
  • RT NDT is the main material of the pressure vessel.
  • the non-ductile transition temperature, its design value is ⁇ -20°C. Therefore, the temperature of the internal components of the metal reactor should not be lower than 13 °C during the cold test of the primary circuit pressure vessel of the high temperature gas-cooled reactor.
  • the 200MW high-temperature gas-cooled reactor demonstration project under construction in China is located in the southeast of Shandong Peninsula.
  • the atmospheric temperature changes in the range of -15°C ⁇ 35°C in one year, resulting in a large temperature change in the primary circuit pressure vessel cabin.
  • the temperature of the metal components in the reactor will be much lower than 13 °C, which does not meet the requirements of the international standard ASME-III-I-NB-6000 for the pressure test.
  • ASME-III-I-NB-6000 Causes brittle fracture of metal stack internals. Therefore, how to increase the temperature of the metal components in the reactor by heating the primary circuit compartment has become a key technical issue in the cold test of the high temperature gas-cooled reactor nuclear power plant.
  • the purpose of the present invention is to overcome the above-mentioned shortcomings of the prior art, and to provide a primary-circuit cabin heating system and method during the cold test of a high-temperature gas-cooled nuclear power plant, which can ensure that the high-temperature gas-cooled nuclear power plant maintains a constant temperature during the cold test.
  • the temperature in the loop cabin is constant, and the temperature of the internal components of the metal stack is increased to meet the requirements of the cold test test.
  • the primary circuit cabin heating system during the cold test of the high temperature gas-cooled reactor nuclear power plant includes a concrete cabin structure, a pressure vessel, a steam generator, a first air inlet pipe, a pressure Container compartment return air duct, second air inlet duct, steam generator compartment hot air blower device and steam generator compartment return air duct;
  • a circuit compartment is arranged in the concrete cabin structure, and the primary circuit compartment is divided into a reactor compartment and a steam generator compartment, wherein the pressure vessel is arranged in the reactor compartment, the steam generator is arranged in the steam generator compartment, the pressure vessel and the steam generator communicated with each other through a hot air duct;
  • first air inlet pipe One end of the first air inlet pipe is communicated with the outlet of the hot air blower device in the pressure vessel cabin, the other end of the first air inlet pipe is inserted into the reactor cabin, and a number of first air outlet nozzles are arranged on the first air inlet pipe, wherein , each first air outlet nozzle is located in the reactor compartment and below the pressure vessel, one end of the return air pipe of the pressure vessel compartment is connected with the inlet of the hot air blower device of the pressure vessel compartment, and the other end of the return air pipe of the pressure vessel compartment is inserted into the in the reactor compartment and above the pressure vessel;
  • One end of the second air inlet pipe is communicated with the outlet of the hot air blower device in the steam generator cabin, the other end of the second air inlet pipe is inserted into the steam generator cabin, and a number of second air outlet pipes are arranged on the second air inlet pipe mouth, wherein each second air outlet nozzle is located in the steam generator cabin and below the steam generator, one end of the return air pipe in the steam generator cabin is communicated with the inlet of the hot air blower device in the steam generator cabin, and the steam generator The other end of the cabin air return pipe is inserted into the steam generator cabin and located above the steam generator.
  • the side wall of the reactor compartment is provided with a pressure vessel manhole for the pressure vessel compartment return air pipe and the first air inlet pipe to pass through.
  • the side wall of the steam generator cabin is provided with a steam generator manhole for the second air inlet pipe and the return air pipe of the steam generator cabin to pass through.
  • the first air outlet nozzles are distributed at equal intervals, and the second air outlet nozzles are distributed at equal intervals.
  • the manhole of the pressure vessel, the manhole of the steam generator, the top of the steam generator and the top of the reactor compartment are all provided with layers of thermal insulation cotton material.
  • the hot fan device in the pressure vessel cabin and the hot fan device in the steam generator cabin include the air supply system of the hot fan device, the heating system of the hot fan device and the temperature control system of the hot fan device.
  • the temperature control system of the hot fan device and the heating system of the hot fan device The control end of the hot air blower device is connected, and the outlet of the air supply system of the hot air blower device is connected with the inlet of the heating system of the hot air blower device;
  • the inlet of the air supply system of the hot fan device in the hot fan device of the pressure vessel cabin is connected with the return air pipe of the steam generator cabin, and the outlet of the heating system of the hot fan device in the hot fan device of the pressure vessel cabin is communicated with the second air inlet pipe;
  • the inlet of the air supply system of the hot fan device in the steam generator cabin hot fan device is connected with the return air pipe of the pressure vessel cabin, and the outlet of the heating system of the hot fan device in the steam generator cabin hot fan device is communicated with the first air inlet pipe.
  • the method for heating the primary circuit cabin during the cold test of the high temperature gas-cooled reactor nuclear power plant according to the present invention comprises the following steps:
  • the primary circuit cold test depressurization process begins, that is, the pressure in the pressure vessel and the steam generator is gradually reduced to normal pressure. During this process, the pressure vessel and steam are maintained. The temperature of the metal components in the generator is constant, and when the emergency pressure relief abnormal condition of weld leakage occurs during the primary circuit cold test depressurization, the heating of the hot air blower device in the pressure vessel compartment and the steam generator compartment hot air device is increased. power and air volume, to avoid the temperature drop of the metal components in the pressure vessel and the steam generator. After the depressurization of the primary circuit cold test, stop the hot air blower device in the pressure vessel compartment and the steam generator compartment hot air blower device.
  • the heating system and method for the primary circuit cabin during the cold test of the high-temperature gas-cooled reactor nuclear power plant increases the temperature of the metal components in the reactor by heating the primary circuit chamber, ensures a constant temperature in the primary circuit cabin, and solves the problem of the external environment.
  • the temperature is low, there is a problem in the cold test of the primary circuit.
  • two hot air blower devices are configured in the present invention, and the heating can make the temperature rise of the primary circuit cabin space evenly distributed and the heating rate is high.
  • it can be According to the air volume and wind speed requirements in the actual project heating process, the input quantity of the first air outlet nozzle and the second air outlet nozzle is flexibly allocated to improve the operability of the heating process.
  • FIG. 1 is a schematic structural diagram of the present invention.
  • 1-pressure vessel cabin hot air blower device 2-pressure vessel, 3-hot air duct, 4-steam generator, 5-first air inlet pipe, 61-first air outlet nozzle, 62-second air outlet Nozzle, 7- pressure vessel cabin return air pipe, 8- steam generator cabin hot air blower device, 9- second air inlet pipe, 10- steam generator cabin return air pipe, 11- pressure vessel manhole, 12- steam Generator manhole, 13-heating system of hot fan device, 14- temperature control system of hot fan device, 15-concrete cabin structure, 16- air supply system of hot fan device.
  • a layer/element when referred to as being "on" another layer/element, it can be directly on the other layer/element or intervening layers/elements may be present therebetween. element.
  • a layer/element when a layer/element is “on” another layer/element in one orientation, then when the orientation is reversed, the layer/element can be "under” the other layer/element.
  • the primary circuit cabin heating system of the present invention includes a concrete cabin structure 15, a pressure vessel 2, a steam generator 4, a first air inlet pipe 5, and a pressure vessel cabin hot air blower during the cold test of the high temperature gas-cooled reactor nuclear power plant.
  • the concrete cabin structure body 15 is provided with a circuit chamber, a circuit chamber
  • the interior is divided into a reactor compartment and a steam generator compartment, wherein the pressure vessel 2 is arranged in the reactor compartment, the steam generator 4 is arranged in the steam generator compartment, and the pressure vessel 2 and the steam generator 4 are connected through a hot gas conduit 3
  • One end of the first air inlet pipe 5 is communicated with the outlet of the pressure vessel cabin hot air blower device 1, the other end of the first air inlet pipe 5 is inserted into the reactor cabin, and the first air inlet pipe 5 is provided with a number of first outlet Air pipe nozzles 61, wherein each first air outlet nozzle 61 is located in the reactor cabin and below the pressure vessel 2, and one end of the return air pipe 7 in the pressure vessel cabin is communicated with the inlet of the hot air blower device 1 in the pressure vessel cabin.
  • the other end of the container cabin return air pipe 7 is inserted into the reactor cabin and is located above the pressure vessel 2; The other end is inserted into the steam generator cabin, and the second air inlet pipe 9 is provided with a plurality of second air outlet nozzles 62, wherein each second air outlet nozzle 62 is located in the steam generator cabin and located in the steam generator.
  • the return air pipe 10 of the steam generator cabin is communicated with the inlet of the steam generator cabin hot air blower device 8, and the other end of the return air pipe 10 of the steam generator cabin is inserted into the steam generator cabin and is located in the steam generator cabin.
  • the first air outlet nozzles 61 are distributed at equal intervals
  • the second air outlet nozzles 62 are distributed at equal intervals.
  • the side wall of the reactor cabin is provided with a pressure vessel manhole 11 for the return air pipe 7 of the pressure vessel cabin and the first air inlet pipe 5 to pass through;
  • the side wall of the steam generator cabin is provided with a second air inlet pipe. 9 and the steam generator manhole 12 through which the return air pipe 10 of the steam generator cabin passes.
  • the manhole 11 of the pressure vessel, the manhole 12 of the steam generator, the top of the steam generator 4 and the top of the reactor compartment are all provided with layers of thermal insulation cotton material.
  • the pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8 both include a hot air blower device air supply system 16 , a hot air fan device heating system 13 and a hot air fan device temperature control system 14 , wherein the hot air fan device temperature control system 14 It is connected with the control end of the heating system 13 of the hot air blower device, and the outlet of the air supply system 16 of the hot air blower device is communicated with the inlet of the heating system 13 of the hot air blower device;
  • the inlet is communicated with the return air pipe 7 of the pressure vessel cabin, the outlet of the heating system 13 of the hot air blower device in the pressure vessel cabin hot air fan device 1 is communicated with the first air inlet pipe 5; the hot air fan device in the steam generator cabin hot air fan device 8
  • the inlet of the air supply system 16 is communicated with the return air pipe 10 of the steam generator cabin, and the outlet of the heating system 13 of the hot fan device in the steam generator cabin hot fan device 8 is communicated with the second air inlet pipe
  • the method for heating the primary circuit cabin during the cold test of the high temperature gas-cooled reactor nuclear power plant according to the present invention comprises the following steps:
  • the first air outlet nozzle 61 and each second air outlet nozzle 62 are equipped with independent plugs. During actual operation, a corresponding number of first air outlet nozzles 61 and The second air outlet nozzle 62, the other spare first air outlet nozzle 61 and the second air outlet nozzle 62 are blocked by plugs.
  • the heating system 13 of the hot air blower device may be composed of electric heating wires or graphene heating materials.
  • the pressure vessel 2 and the steam generator 4 are in the normal pressure state.
  • the total heating power and total air volume of the hot air blower device 1 in the pressure vessel compartment and the hot air blower device 8 in the steam generator compartment are obtained.
  • the temperature of the metal components in the reactor meets the requirement of not lower than 13°C, the temperature of the primary circuit cabin needs to be maintained at about 30°C, and the total effective heating power to be input during the period is about 300KW, considering the heat loss of 20% to 25%, The total effective heating power needs to be 380 ⁇ 400KW, and the air volume demand is 33200 ⁇ 44000m 3 /h;
  • the air supply system 16 of the hot air blower device blows the ambient air of the primary circuit cabin to the hot air blower device heating system 13, and the air passes through the hot air blower device heating system In 13, the heating wire or the graphene heating material is heated and sent into the first air outlet nozzle 61 and the second air outlet nozzle 62, and the hot air after being heated by the hot air fan device temperature control system 14 is detected at the same time temperature, and adjust the heating power of the heating system 13 of the hot fan device according to the temperature of the air heated by the heating system 13 of the hot fan device, so as to gradually increase the temperature of the primary circuit cabin to 30°C.
  • the hot air blower device 1 in the pressure vessel compartment and the hot air blower device 8 in the steam generator compartment are adjusted to a balanced state and keep running continuously.
  • the temperature of the primary circuit compartment is kept constant to 30°C;
  • the primary circuit cold test depressurization process begins, the pressure in the pressure vessel 2 and the steam generator 4 is gradually reduced to normal pressure, and the temperature of the metal components is maintained constant during the test.
  • the hot air blower device 1 of the pressure vessel compartment and the steam generator compartment adjust the hot air blower device 1 of the pressure vessel compartment and the steam generator compartment.
  • the heating power and air volume of the hot air blower device 8 can prevent the temperature of the metal components in the pressure vessel 2 and the steam generator 4 from dropping rapidly.
  • the hot air blower device 1 in the pressure vessel compartment and the hot air blower device 8 in the steam generator compartment are stopped.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
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Abstract

一种高温气冷堆核电站冷试期间一回路舱室加热系统及方法，包括混凝土舱室结构体(15)、压力容器(2)、蒸汽发生器(4)、第一进风管(5)、压力容器舱室热风机装置(1)、压力容器舱室回风管(7)、第二进风管(9)、蒸汽发生器舱室热风机装置(8)及蒸汽发生器舱室回风管(10)，高温气冷堆核电站冷试期间一回路舱室加热系统及方法能够保证在高温其冷堆核电站冷试期间维持一回路舱室内温度恒定，提升金属堆内构件温度，满足冷试试验要求。

Description

一种高温气冷堆核电站冷试期间一回路舱室加热系统及方法 技术领域
本发明属于核电技术领域，涉及一种高温气冷堆核电站冷试期间一回路舱室加热系统及方法。
背景技术
核电站冷试是核电站完成土建施工、设备安装和单系统调试后，对核岛关键设备性能和安装工艺质量进行的联合调试验证，目的是通过验证一回路系统的密封性和强度来评估核安全保护屏障的完整性，并获得一回路系统和设备的初始运行数据。一回路压力容器是一回路压力边界的主体，其强度和密封性能对于保证反应堆的安全运行至关重要。根据核安全法规的要求，冷试期间需进行一回路压力边界的强度和密封性能试验，一回路系统冷态役前压力试验为核电站冷试的主要试验内容。
不同于压水堆核电机组进行的一回路水压试验，高温气冷堆一回路以氦气为冷却剂，其采用气压试验的方式。根据国际标准ASME-III-I-NB-6000中规定：对于反应堆压力容器装料前所进行的系统压力试验，试验温度不应低于RT NDT+33℃，其中RT NDT是压力容器主体材料的无延性转变温度，其设计值为≤﹣20℃。因此，高温气冷堆一回路压力容器在冷试过程中金属堆内构件温度不应低于13℃。同时，由于氦气为小分子气体，气压试验期间需保证其泄漏率满足设计要求。为了避免环境温度对泄漏率监测计算值的影响，一回路冷试期间需尽量保证一回路压力容器内部温度恒定。基于以上原因，高温气冷堆一回路冷试期间需保证压力容器舱室环境温度恒定。
目前国内在建的200MW高温气冷堆示范工程厂址位于山东半岛东南部，一年中大气环境温度变化范围为﹣15℃～35℃，导致一回路压力容器舱室温度变化较大。当在外部环境较低的冬季进行一回路冷试时，反应堆内金属构件温度将远低于13℃，不符合国际标准ASME-III-I-NB-6000对压力试验的规定，严重情况下将导致金属堆内构件的脆性断裂。因此，如何通过加热一回路舱室来提升反应堆内金属构件的温度，已成为高温气冷堆核电站冷试的关键技术问题。
发明内容
本发明的目的在于克服上述现有技术的缺点，提供了一种高温气冷堆核电站冷试期间一回路舱室加热系统及方法，该系统及方法能够保证高温气冷堆核电站在冷试期间维持一回路舱室内温度恒定，提升金属堆内构件温度，满足冷试试验要求。
为达到上述目的，本发明所述的高温气冷堆核电站冷试期间一回路舱室加热系统包括混凝土舱室结构体、压力容器、蒸汽发生器、第一进风管、压力容器舱室热风机装置、压力容器舱室回风管、第二进风管、蒸汽发生器舱室热风机装置及蒸汽发生器舱室回风管；
混凝土舱室结构体内设置有一回路舱室，一回路舱室内分隔为反应堆舱室及蒸汽发生器舱室，其中，压力容器布置于反应堆舱室内，蒸汽发生器布置于蒸汽发生器舱室内，压力容器与蒸汽发生器之间通过热气导管相连通；
第一进风管的一端与压力容器舱室热风机装置的出口相连通，第一进风管的另一端插入到反应堆舱室内，第一进风管上设置有若干第一出风管嘴，其中，各第一出风管嘴位于反应堆舱室内且位于压力容器的下方，压力容器舱室回风管的一端与压力容器舱室热风机装置的入口相连通，压力容器舱室回风管的另一端插 入于反应堆舱室内且位于压力容器的上方；
第二进风管的一端与蒸汽发生器舱室热风机装置的出口相连通，第二进风管的另一端插入于蒸汽发生器舱室内，第二进风管上设置有若干第二出风管嘴，其中，各第二出风管嘴位于蒸汽发生器舱室内且位于蒸汽发生器的下方，蒸汽发生器舱室回风管的一端与蒸汽发生器舱室热风机装置的入口相连通，蒸汽发生器舱室回风管的另一端插入于蒸汽发生器舱室内且位于蒸汽发生器的上方。
反应堆舱室的侧壁上设置有用于供压力容器舱室回风管及第一进风管穿过的压力容器人孔。
蒸汽发生器舱室的侧壁上设置有用于供第二进风管及蒸汽发生器舱室回风管穿过的蒸汽发生器人孔。
各第一出风管嘴等间距分布，各第二出风管嘴等间距分布。
压力容器人孔、蒸汽发生器人孔、蒸汽发生器的顶部及反应堆舱室的顶部均敷设隔热保温棉材料层。
压力容器舱室热风机装置及蒸汽发生器舱室热风机装置均包括热风机装置送风系统、热风机装置加热系统及热风机装置温控系统，其中，热风机装置温控系统与热风机装置加热系统的控制端相连接，热风机装置送风系统的出口与热风机装置加热系统的入口相连通；
压力容器舱室热风机装置中热风机装置送风系统的入口与蒸汽发生器舱室回风管相连通，压力容器舱室热风机装置中热风机装置加热系统的出口与第二进风管相连通；
蒸汽发生器舱室热风机装置中热风机装置送风系统的入口与压力容器舱室回风管相连通，蒸汽发生器舱室热风机装置中热风机装置加热系统的出口与第一 进风管相连通。
本发明所述的高温气冷堆核电站冷试期间一回路舱室加热方法包括以下步骤：
1)高温气冷堆冷试开始前，压力容器和蒸汽发生器处于常压状态，根据压力容器及蒸汽发生器内金属构件和一回路舱室的环境温度，计算压力容器舱室热风机装置及蒸汽发生器舱室热风机装置所需加热的总功率及总风量；
2)启动压力容器舱室热风机装置和蒸汽发生器舱室热风机装置，通过第一出风管嘴及第二出风管嘴分别向蒸汽发生器舱室及反应堆舱室内吹入热风，逐步提升蒸汽发生器舱室及反应堆舱室内的温度，当压力容器和蒸汽发生器内金属构件的温度满足试验要求时，通过压力容器舱室热风机装置及蒸汽发生器舱室热风机装置维持蒸汽发生器舱室及反应堆舱室内的温度恒定；
3)开始进行一回路冷试期间耐压试验，向压力容器和蒸汽发生器内充入空气，将压力容器和蒸汽发生器内的压力升至最高试验压力，进行一回路泄漏率和压力容器的焊缝检测，在此过程中，实时监测压力容器和蒸汽发生器内金属构件的温度，通过动态调整压力容器舱室热风机装置和蒸汽发生器舱室热风机装置的加热功率及风量来维持压力容器和蒸汽发生器内金属构件的温度恒定；
4)一回路冷试期间耐压试验完成后，开始进行一回路冷试降压过程，即将压力容器和蒸汽发生器内的压力逐步降压至常压，在此过程中，维持压力容器和蒸汽发生器内金属构件的温度恒定，其中，当一回路冷试降压期间发生焊缝泄漏的紧急泄压异常工况时，则提高压力容器舱室热风机装置和蒸汽发生器舱室热风机装置的加热功率及风量，避免压力容器和蒸汽发生器内金属构件的温度下降，一回路冷试降压结束后，停运压力容器舱室热风机装置和蒸汽发生器舱室热风机 装置。
本发明具有以下有益效果：
本发明所述的高温气冷堆核电站冷试期间一回路舱室加热系统及方法在具体操作时，通过加热一回路舱室来提升反应堆内金属构件的温度，保证一回路舱室内温度恒定，解决外部环境温度较低时进行一回路冷试存在的问题，另外，本发明中配置两台热风机装置，同时加热使得一回路舱室空间温升分布均匀，升温速率较高，另外，在实际操作时，可以根据实际工程加热过程中风量和风速需求，灵活分配第一出风管嘴及第二出风管嘴的投入数量，提高加热过程的可操作性。
附图说明
为了更清楚的说明本发明实施例的技术方案，下面将对实施例中所需要使用的附图作简单地介绍，应当理解，以下附图仅示出了本发明的某些实施例，因此不应被看作是对范围的限定，对于本领域普通技术人员来讲，在不付出创造性劳动的前提下，还可以根据这些附图获得其他相关的附图。
图1为本发明的结构示意图。
其中，1-压力容器舱室热风机装置，2-压力容器，3-热气导管，4-蒸汽发生器，5-第一进风管，61-第一出风管嘴，62-第二出风管嘴，7-压力容器舱室回风管，8-蒸汽发生器舱室热风机装置，9-第二进风管，10-蒸汽发生器舱室回风管，11-压力容器人孔，12-蒸汽发生器人孔，13-热风机装置加热系统，14-热风机装置温控系统，15-混凝土舱室结构体，16-热风机装置送风系统。
具体实施方式
为了使本技术领域的人员更好地理解本发明方案，下面将结合本发明实施例 中的附图，对本发明实施例中的技术方案进行清楚、完整地描述，显然，所描述的实施例仅仅是本发明一部分的实施例，不是全部的实施例，而并非要限制本发明公开的范围。此外，在以下说明中，省略了对公知结构和技术的描述，以避免不必要的混淆本发明公开的概念。基于本发明中的实施例，本领域普通技术人员在没有做出创造性劳动前提下所获得的所有其他实施例，都应当属于本发明保护的范围。
在附图中示出了根据本发明公开实施例的各种结构示意图。这些图并非是按比例绘制的，其中为了清楚表达的目的，放大了某些细节，并且可能省略了某些细节。图中所示出的各种区域、层的形状及它们之间的相对大小、位置关系仅是示例性的，实际中可能由于制造公差或技术限制而有所偏差，并且本领域技术人员根据实际所需可以另外设计具有不同形状、大小、相对位置的区域/层。
本发明公开的上下文中，当将一层/元件称作位于另一层/元件“上”时，该层/元件可以直接位于该另一层/元件上，或者它们之间可以存在居中层/元件。另外，如果在一种朝向中一层/元件位于另一层/元件“上”，那么当调转朝向时，该层/元件可以位于该另一层/元件“下”。
需要说明的是，本发明的说明书和权利要求书及上述附图中的术语“第一”、“第二”等是用于区别类似的对象，而不必用于描述特定的顺序或先后次序。应该理解这样使用的数据在适当情况下可以互换，以便这里描述的本发明的实施例能够以除了在这里图示或描述的那些以外的顺序实施。此外，术语“包括”和“具有”以及他们的任何变形，意图在于覆盖不排他的包含，例如，包含了一系列步骤或单元的过程、方法、系统、产品或设备不必限于清楚地列出的那些步骤或单元，而是可包括没有清楚地列出的或对于这些过程、方法、产品或设备固有的其它步 骤或单元。
下面结合附图对本发明做进一步详细描述：
参考图1，本发明所述的高温气冷堆核电站冷试期间一回路舱室加热系统包括混凝土舱室结构体15、压力容器2、蒸汽发生器4、第一进风管5、压力容器舱室热风机装置1、压力容器舱室回风管7、第二进风管9、蒸汽发生器舱室热风机装置8及蒸汽发生器舱室回风管10；混凝土舱室结构体15内设置有一回路舱室，一回路舱室内分隔为反应堆舱室及蒸汽发生器舱室，其中，压力容器2布置于反应堆舱室内，蒸汽发生器4布置于蒸汽发生器舱室内，压力容器2与蒸汽发生器4之间通过热气导管3相连通；第一进风管5的一端与压力容器舱室热风机装置1的出口相连通，第一进风管5的另一端插入到反应堆舱室内，第一进风管5上设置有若干第一出风管嘴61，其中，各第一出风管嘴61位于反应堆舱室内且位于压力容器2的下方，压力容器舱室回风管7的一端与压力容器舱室热风机装置1的入口相连通，压力容器舱室回风管7的另一端插入于反应堆舱室内且位于压力容器2的上方；第二进风管9的一端与蒸汽发生器舱室热风机装置8的出口相连通，第二进风管9的另一端插入于蒸汽发生器舱室内，第二进风管9上设置有若干第二出风管嘴62，其中，各第二出风管嘴62位于蒸汽发生器舱室内且位于蒸汽发生器4的下方，蒸汽发生器舱室回风管10的一端与蒸汽发生器舱室热风机装置8的入口相连通，蒸汽发生器舱室回风管10的另一端插入于蒸汽发生器舱室内且位于蒸汽发生器4的上方，各第一出风管嘴61等间距分布，各第二出风管嘴62等间距分布。
反应堆舱室的侧壁上设置有用于供压力容器舱室回风管7及第一进风管5穿过的压力容器人孔11；蒸汽发生器舱室的侧壁上设置有用于供第二进风管9及蒸 汽发生器舱室回风管10穿过的蒸汽发生器人孔12。
压力容器人孔11、蒸汽发生器人孔12、蒸汽发生器4的顶部及反应堆舱室的顶部均敷设隔热保温棉材料层。
压力容器舱室热风机装置1及蒸汽发生器舱室热风机装置8均包括热风机装置送风系统16、热风机装置加热系统13及热风机装置温控系统14，其中，热风机装置温控系统14与热风机装置加热系统13的控制端相连接，热风机装置送风系统16的出口与热风机装置加热系统13的入口相连通；压力容器舱室热风机装置1中热风机装置送风系统16的入口与压力容器舱室回风管7相连通，压力容器舱室热风机装置1中热风机装置加热系统13的出口与第一进风管5相连通；蒸汽发生器舱室热风机装置8中热风机装置送风系统16的入口与蒸汽发生器舱室回风管10相连通，蒸汽发生器舱室热风机装置8中热风机装置加热系统13的出口与第二进风管9相连通。
本发明所述的高温气冷堆核电站冷试期间一回路舱室加热方法包括以下步骤：
1)高温气冷堆冷试开始前，压力容器2和蒸汽发生器4处于常压状态，根据压力容器2及蒸汽发生器4内金属构件和一回路舱室的环境温度，计算压力容器舱室热风机装置1及蒸汽发生器舱室热风机装置8所需加热的总功率及总风量；
2)启动压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8，通过第一出风管嘴61及第二出风管嘴62分别向蒸汽发生器舱室及反应堆舱室内吹入热风，逐步提升蒸汽发生器舱室及反应堆舱室内的温度，当压力容器2和蒸汽发生器4内金属构件的温度满足试验要求时，通过压力容器舱室热风机装置1及蒸汽发生器舱室热风机装置8维持蒸汽发生器舱室及反应堆舱室内的温度恒定；
3)开始进行一回路冷试期间耐压试验，向压力容器2和蒸汽发生器4内充入空气，将压力容器2和蒸汽发生器4内的压力升至最高试验压力，进行一回路泄漏率和压力容器2的焊缝检测，在此过程中，实时监测压力容器2和蒸汽发生器4内金属构件的温度，通过动态调整压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8的加热功率及风量来维持压力容器2和蒸汽发生器4内金属构件的温度恒定；
4)一回路冷试期间耐压试验完成后，开始进行一回路冷试降压过程，即将压力容器2和蒸汽发生器4内的压力逐步降压至常压，在此过程中，维持压力容器2和蒸汽发生器4内金属构件的温度恒定，其中，当一回路冷试降压期间发生焊缝泄漏的紧急泄压异常工况时，则提高压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8的加热功率及风量，避免压力容器2和蒸汽发生器4内金属构件的温度下降，一回路冷试降压结束后，停运压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8。
第一出风管嘴61及各第二出风管嘴62均配置有独立的堵头，在实际操作时，可根据出风口风量和风速需求来投入相应数量的第一出风管嘴61及第二出风管嘴62，其它备用第一出风管嘴61及第二出风管嘴62通过堵头堵塞。
热风机装置加热系统13可以由电热丝或石墨烯发热材料组成。
实施例一
以目前正在建设的200MW高温气冷堆示范工程为例，本发明的具体工作过程为：
1)高温气冷堆冷试开始前，压力容器2和蒸汽发生器4处于常压状态，根据压力容器2及蒸汽发生器4内金属构件和一回路舱室的环境温度，计算校核所 需的压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8的加热总功率及总风量。以冷试期间一回路舱室温度为5℃为试验工况，根据高温气冷堆一回路舱室几何体尺寸以及压力容器2和蒸汽发生器4及其金属构件的主要技术参数为计算依据，计算得出：反应堆内金属构件温度满足不低于13℃要求的情况下，一回路舱室温度需维持在30℃左右，期间需输入的总有效加热功率约为300KW，考虑20％～25％的热损耗，总有效加热功率需为380～400KW，风量需求为33200～44000m 3/h；
2)启动压力容器舱室热风机装置1及蒸汽发生器舱室热风机装置8，由热风机装置送风系统16将一回路舱室环境空气吹送到热风机装置加热系统13，空气通过热风机装置加热系统13中电热丝或石墨烯发热材料加热后送入第一出风管嘴61及第二出风管嘴62内，同时通过热风机装置温控系统14检测热风机装置加热系统13加热后热空气温度，并根据热风机装置加热系统13加热后风的温度调节热风机装置加热系统13的加热功率，以逐步提升一回路舱室的温度至30℃。当压力容器2和蒸汽发生器4内金属构件温度满足试验要求(不低于13℃)，压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8调整至平衡状态并保持连续运行，维持一回路舱室温度恒定至30℃；
3)压力容器2和蒸汽发生器4内开始充入空气，开始一回路冷试升压试验，逐步将压力容器2和蒸汽发生器4内的压力升至最高试验压力9.0MPa，进行一回路泄漏率和压力容器2焊缝检测，该阶段需实时监测压力容器2和蒸汽发生器4内金属构件的温度，通过动态调整压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8的加热功率和风量，以维持金属构件温度恒定；
4)一回路冷试期间耐压试验完成后，开始一回路冷试降压过程，压力容器2 和蒸汽发生器4内的压力逐步降压至常压，试验中维持金属构件温度恒定，在此过程中，当一回路冷试期间发生焊缝不合格，泄漏率不满足标准(≤0.1％/d)等紧急泄压异常工况时，则调整压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8的加热功率和风量，避免压力容器2和蒸汽发生器4内金属构件温度快速下降，试验结束后，停运压力容器舱室热风机装置1和蒸汽发生器舱室热风机装置8。
以上内容仅为说明本发明的技术思想，不能以此限定本发明的保护范围，凡是按照本发明提出的技术思想，在技术方案基础上所做的任何改动，均落入本发明权利要求书的保护范围之内。

Claims (7)

  1. 一种高温气冷堆核电站冷试期间一回路舱室加热系统，其特征在于，包括混凝土舱室结构体(15)、压力容器(2)、蒸汽发生器(4)、第一进风管(5)、压力容器舱室热风机装置(1)、压力容器舱室回风管(7)、第二进风管(9)、蒸汽发生器舱室热风机装置(8)及蒸汽发生器舱室回风管(10)；
    混凝土舱室结构体(15)内设置有一回路舱室，一回路舱室内分隔为反应堆舱室及蒸汽发生器舱室，其中，压力容器(2)布置于反应堆舱室内，蒸汽发生器(4)布置于蒸汽发生器舱室内，压力容器(2)与蒸汽发生器(4)之间通过热气导管(3)相连通；
    第一进风管(5)的一端与压力容器舱室热风机装置(1)的出口相连通，第一进风管(5)的另一端插入到反应堆舱室内，第一进风管(5)上设置有若干第一出风管嘴(61)，其中，各第一出风管嘴(61)位于反应堆舱室内且位于压力容器(2)的下方，压力容器舱室回风管(7)的一端与压力容器舱室热风机装置(1)的入口相连通，压力容器舱室回风管(7)的另一端插入于反应堆舱室内且位于压力容器(2)的上方；
    第二进风管(9)的一端与蒸汽发生器舱室热风机装置(8)的出口相连通，第二进风管(9)的另一端插入于蒸汽发生器舱室内，第二进风管(9)上设置有若干第二出风管嘴(62)，其中，各第二出风管嘴(62)位于蒸汽发生器舱室内且位于蒸汽发生器(4)的下方，蒸汽发生器舱室回风管(10)的一端与蒸汽发生器舱室热风机装置(8)的入口相连通，蒸汽发生器舱室回风管(10)的另一端插入于蒸汽发生器舱室内且位于蒸汽发生器(4)的上方。
  2. 根据权利要求1所述的高温气冷堆核电站冷试期间一回路舱室加热系统，其特征在于，反应堆舱室的侧壁上设置有用于供压力容器舱室回风管(7)及第 一进风管(5)穿过的压力容器人孔(11)。
  3. 根据权利要求1所述的高温气冷堆核电站冷试期间一回路舱室加热系统，其特征在于，蒸汽发生器舱室的侧壁上设置有用于供第二进风管(9)及蒸汽发生器舱室回风管(10)穿过的蒸汽发生器人孔(12)。
  4. 根据权利要求1所述的高温气冷堆核电站冷试期间一回路舱室加热系统，其特征在于，各第一出风管嘴(61)等间距分布，各第二出风管嘴(62)等间距分布。
  5. 根据权利要求1所述的高温气冷堆核电站冷试期间一回路舱室加热系统，其特征在于，压力容器人孔(11)、蒸汽发生器人孔(12)、蒸汽发生器(4)的顶部及反应堆舱室的顶部均敷设隔热保温棉材料层。
  6. 根据权利要求1所述的高温气冷堆核电站冷试期间一回路舱室加热系统，其特征在于，压力容器舱室热风机装置(1)及蒸汽发生器舱室热风机装置(8)均包括热风机装置送风系统(16)、热风机装置加热系统(13)及热风机装置温控系统(14)，其中，热风机装置温控系统(14)与热风机装置加热系统(13)的控制端相连接，热风机装置送风系统(16)的出口与热风机装置加热系统(13)的入口相连通；
    压力容器舱室热风机装置(1)中热风机装置送风系统(16)的入口与蒸汽发生器舱室回风管(10)相连通，压力容器舱室热风机装置(1)中热风机装置加热系统(13)的出口与第二进风管(9)相连通；
    蒸汽发生器舱室热风机装置(8)中热风机装置送风系统(16)的入口与压力容器舱室回风管(7)相连通，蒸汽发生器舱室热风机装置(8)中热风机装置加热系统(13)的出口与第一进风管(5)相连通。
  7. 一种高温气冷堆核电站冷试期间一回路舱室加热方法，其特征在于，包括以下步骤：
    1)高温气冷堆冷试开始前，压力容器(2)和蒸汽发生器(4)处于常压状态，根据压力容器(2)及蒸汽发生器(4)内金属构件和一回路舱室的环境温度，计算压力容器舱室热风机装置(1)及蒸汽发生器舱室热风机装置(8)所需加热的总功率及总风量；
    2)启动压力容器舱室热风机装置(1)和蒸汽发生器舱室热风机装置(8)，通过第一出风管嘴(61)及第二出风管嘴(62)分别向蒸汽发生器舱室及反应堆舱室内吹入热风，逐步提升蒸汽发生器舱室及反应堆舱室内的温度，当压力容器(2)和蒸汽发生器(4)内金属构件的温度满足试验要求时，通过压力容器舱室热风机装置(1)及蒸汽发生器舱室热风机装置(8)维持蒸汽发生器舱室及反应堆舱室内的温度恒定；
    3)开始进行一回路冷试期间耐压试验，向压力容器(2)和蒸汽发生器(4)内充入空气，将压力容器(2)和蒸汽发生器(4)内的压力升至最高试验压力，进行一回路泄漏率和压力容器(2)的焊缝检测，在此过程中，实时监测压力容器(2)和蒸汽发生器(4)内金属构件的温度，通过动态调整压力容器舱室热风机装置(1)和蒸汽发生器舱室热风机装置(8)的加热功率及风量来维持压力容器(2)和蒸汽发生器(4)内金属构件的温度恒定；
    4)一回路冷试期间耐压试验完成后，开始进行一回路冷试降压过程，即将压力容器(2)和蒸汽发生器(4)内的压力逐步降压至常压，在此过程中，维持压力容器(2)和蒸汽发生器(4)内金属构件的温度恒定，其中，当一回路冷试降压期间发生焊缝泄漏的紧急泄压异常工况时，则提高压力容器舱室热风机装置 (1)和蒸汽发生器舱室热风机装置(8)的加热功率及风量，避免压力容器(2)和蒸汽发生器(4)内金属构件的温度下降，一回路冷试降压结束后，停运压力容器舱室热风机装置(1)和蒸汽发生器舱室热风机装置(8)。
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