阅读说明：本技术 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 (Heating system and method for primary loop cabin during cold test of high-temperature gas cooled reactor nuclear power station ) 是由 刘俊峰 于 2020-07-21 设计创作，主要内容包括：本发明公开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,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,该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。(The invention discloses a primary loop cabin heating system and a primary loop cabin heating method during a cold test period of a high-temperature gas cooled reactor nuclear power station.)

1. A primary loop cabin heating system during cold test of a high-temperature gas cooled reactor nuclear power station is characterized by comprising a concrete cabin structural body (15), a pressure vessel (2), a steam generator (4), a first air inlet pipe (5), a pressure vessel cabin air heater device (1), a pressure vessel cabin return air pipe (7), a second air inlet pipe (9), a steam generator cabin air heater device (8) and a steam generator cabin return air pipe (10);

a primary loop cabin is arranged in the concrete cabin structure body (15), the primary loop cabin is divided into a reactor cabin and a steam generator cabin, wherein the pressure vessel (2) is arranged in the reactor cabin, the steam generator (4) is arranged in the steam generator cabin, and the pressure vessel (2) is communicated with the steam generator (4) through a hot gas guide pipe (3);

one end of a first air inlet pipe (5) is communicated with an outlet of a pressure vessel cabin hot air blower device (1), the other end of the first air inlet pipe (5) is inserted into a reactor cabin, a plurality of first air outlet nozzles (61) are arranged on the first air inlet pipe (5), each first air outlet nozzle (61) is positioned in the reactor cabin and below a pressure vessel (2), one end of a pressure vessel cabin return air pipe (7) is communicated with an inlet of the pressure vessel cabin hot air blower device (1), and the other end of the pressure vessel cabin return air pipe (7) is inserted into the reactor cabin and above the pressure vessel (2);

the one end of second air-supply line (9) is linked together with the export of steam generator cabin air heater device (8), the other end of second air-supply line (9) inserts in the steam generator cabin, be provided with a plurality of second air-out mouthpiece (62) on second air-supply line (9), wherein, each second air-out mouthpiece (62) is located the steam generator cabin and is located the below of steam generator (4), the one end of steam generator cabin return air pipe (10) is linked together with the entry of steam generator cabin air heater device (8), the other end of steam generator cabin return air pipe (10) inserts in the steam generator cabin and is located the top of steam generator (4).

2. The primary loop cabin heating system during the cold test of the high temperature gas cooled reactor nuclear power plant as claimed in claim 1, characterized in that a pressure vessel manhole (11) for a pressure vessel cabin return air pipe (7) and a first air inlet pipe (5) to pass through is arranged on the side wall of the reactor cabin.

3. The primary loop compartment heating system during the cold test of the high temperature gas cooled reactor nuclear power plant as claimed in claim 1, wherein a steam generator manhole (12) for passing through the second air inlet pipe (9) and the steam generator compartment return air pipe (10) is provided on the side wall of the steam generator compartment.

4. The primary loop cabin heating system during the cold test of the high temperature gas cooled reactor nuclear power plant as recited in claim 1, wherein each first outlet nozzle (61) is distributed at equal intervals, and each second outlet nozzle (62) is distributed at equal intervals.

5. The primary loop cabin heating system during the cold test of the high temperature gas cooled reactor nuclear power plant according to claim 1, characterized in that the manholes (11) of the pressure vessel, the manholes (12) of the steam generator, the top of the steam generator (4) and the top of the reactor cabin are all laid with a layer of heat insulating and preserving cotton material.

6. The primary loop cabin heating system during the cold test of the high temperature gas cooled reactor nuclear power plant as recited in claim 1, wherein the pressure vessel cabin hot air blower device (1) and the steam generator cabin hot air blower device (8) each comprise a hot air blower device air supply system (16), a hot air blower device heating system (13) and a hot air blower device temperature control system (14), wherein the hot air blower device temperature control system (14) is connected to a control end of the hot air blower device heating system (13), and an outlet of the hot air blower device air supply system (16) is communicated with an inlet of the hot air blower device heating system (13);

an inlet of an air supply system (16) of a hot air blower device in the pressure container cabin hot air blower device (1) is communicated with a steam generator cabin return air pipe (10), and an outlet of a heating system (13) of the hot air blower device in the pressure container cabin hot air blower device (1) is communicated with a second air inlet pipe (9);

an inlet of an air supply system (16) of a hot air blower device in the steam generator cabin hot air blower device (8) is communicated with a pressure vessel cabin return air pipe (7), and an outlet of a heating system (13) of the hot air blower device in the steam generator cabin hot air blower device (8) is communicated with the first air inlet pipe (5).

7. A method for heating a primary loop cabin during cold test of a high-temperature gas cooled reactor nuclear power station is characterized by comprising the following steps:

1) before a cold test of the high-temperature gas cooled reactor is started, the pressure vessel (2) and the steam generator (4) are in a normal pressure state, and the total power and the total air volume required to be heated by the hot air blower device (1) of the pressure vessel cabin and the hot air blower device (8) of the steam generator cabin are calculated according to the ambient temperatures of metal components and a primary loop cabin in the pressure vessel (2) and the steam generator (4);

2) starting a pressure vessel cabin hot air blower device (1) and a steam generator cabin hot air blower device (8), respectively blowing hot air into a steam generator cabin and a reactor cabin through a first air outlet nozzle (61) and a second air outlet nozzle (62), gradually increasing the temperature in the steam generator cabin and the reactor cabin, and maintaining the temperature in the steam generator cabin and the reactor cabin to be constant through the pressure vessel cabin hot air blower device (1) and the steam generator cabin hot air blower device (8) when the temperature of metal components in a pressure vessel (2) and a steam generator (4) meets the test requirements;

3) starting a pressure test during a primary loop cold test, filling air into the pressure vessel (2) and the steam generator (4), raising the pressure in the pressure vessel (2) and the steam generator (4) to the highest test pressure, detecting the leakage rate of the primary loop and the welding seam of the pressure vessel (2), monitoring the temperature of metal components in the pressure vessel (2) and the steam generator (4) in real time in the process, and maintaining the temperature of the metal components in the pressure vessel (2) and the steam generator (4) to be constant by dynamically adjusting the heating power and the air volume of a pressure vessel cabin hot air blower device (1) and a steam generator cabin hot air blower device (8);

4) after a pressure test in a primary loop cold test period is completed, a primary loop cold test pressure reduction process is started, namely, the pressure in the pressure vessel (2) and the pressure in the steam generator (4) are gradually reduced to normal pressure, in the process, the temperature of metal components in the pressure vessel (2) and the temperature of metal components in the steam generator (4) are kept constant, wherein when an emergency pressure reduction abnormal working condition of welding line leakage occurs in the primary loop cold test pressure reduction period, the heating power and the air quantity of the pressure vessel cabin hot air blower device (1) and the steam generator cabin hot air blower device (8) are improved, the temperature reduction of the metal components in the pressure vessel (2) and the steam generator (4) is avoided, and after the primary loop cold test pressure reduction is completed, the pressure vessel cabin hot air blower device (1) and the steam generator hot air blower device (8) are.

Technical Field

The invention belongs to the technical field of nuclear power, and relates to a system and a method for heating a primary loop cabin during a cold test period of a high-temperature gas cooled reactor nuclear power station.

Background

The cold test of the nuclear power station is combined debugging and verification of the performance and the installation process quality of key equipment of a nuclear island after the nuclear power station completes civil construction, equipment installation and single system debugging, and aims to evaluate the integrity of a nuclear safety protection barrier by verifying the tightness and the strength of a loop system and obtain initial operation data of the loop system and the equipment. The primary pressure vessel is the main body of the primary pressure boundary, and the strength and the sealing performance of the primary pressure vessel are important for ensuring the safe operation of the reactor. According to the requirements of nuclear safety laws and regulations, a primary loop pressure boundary strength and sealing performance test is required during a cold test period, and a primary loop system pre-cold-state pre-service pressure test is the main test content of the nuclear power station cold test.

Different from a primary circuit hydraulic test carried out by a pressurized water reactor nuclear power unit, the primary circuit of the high-temperature gas cooled reactor takes helium as a coolant and adopts a gas pressure test mode. According to the international standard ASME-III-I-NB-6000: for system pressure tests conducted prior to charging of the reactor pressure vessel, the test temperature should not be below RT_NDT+33 ℃ where RT_NDTThe non-ductile transition temperature of the main body material of the pressure vessel is less than or equal to-20 ℃. Therefore, the temperature of the internal components of the primary circuit pressure vessel of the high-temperature gas cooled reactor during cold test is not lower than 13 ℃. Meanwhile, since helium is a small molecular gas, the leakage rate of helium during a gas pressure test needs to be ensured to meet design requirements. In order to avoid the influence of the ambient temperature on the leakage rate monitoring calculation value, the internal temperature of the primary circuit pressure container needs to be kept constant as much as possible during the cold test of the primary circuit. For the reasons, the constant ambient temperature of the cabin of the pressure vessel needs to be ensured during the primary loop cold test of the high-temperature gas cooled reactor.

At present, a 200MW high-temperature gas cooled reactor demonstration engineering plant built in China is located in the southeast of the Shandong peninsula, and the atmospheric environment temperature change range is-15-35 ℃ in one year, so that the temperature change of a cabin of a primary circuit pressure vessel is large. When a primary circuit cold test is carried out in winter with lower external environment, the temperature of the metal components in the reactor is far lower than 13 ℃, the temperature of the metal components does not meet the requirement of the international standard ASME-III-I-NB-6000 on pressure test, and the brittle fracture of the metal components in the reactor can be caused in severe cases. Therefore, how to raise the temperature of the metal components in the reactor by heating the primary chamber has become a key technical problem for the cold test of the high temperature gas cooled reactor nuclear power plant.

Disclosure of Invention

The invention aims to overcome the defects of the prior art and provides a system and a method for heating a primary loop cabin during a cold test of a high-temperature gas-cooled reactor nuclear power station.

In order to achieve the purpose, the primary loop cabin heating system during the cold test of the high-temperature gas cooled reactor nuclear power station comprises a concrete cabin structural body, a pressure vessel, a steam generator, a first air inlet pipe, a pressure vessel cabin hot air blower device, a pressure vessel cabin return air pipe, a second air inlet pipe, a steam generator cabin hot air blower device and a steam generator cabin return air pipe;

a primary loop cabin is arranged in the concrete cabin structure body, and the interior of the primary loop cabin is divided into a reactor cabin and a steam generator cabin, wherein a pressure vessel is arranged in the reactor cabin, the steam generator is arranged in the steam generator cabin, and the pressure vessel is communicated with the steam generator through a hot gas conduit;

one end of a first air inlet pipe is communicated with an outlet of the pressure vessel cabin hot air blower device, the other end of the first air inlet pipe is inserted into the reactor cabin, and a plurality of first air outlet nozzles are arranged on the first air inlet pipe, wherein each first air outlet nozzle is positioned in the reactor cabin and below the pressure vessel;

the one end of second air-supply line is linked together with the export of steam generator cabin air heater device, the other end of second air-supply line inserts in the steam generator cabin, be provided with a plurality of second air-out mouthpiece on the second air-supply line, wherein, each second air-out mouthpiece is located the steam generator cabin and is located steam generator's below, the one end of steam generator cabin return air pipe is linked together with the entry of steam generator cabin air heater device, the other end of steam generator cabin return air pipe inserts in the steam generator cabin and is located steam generator's top.

And a pressure container manhole through which a pressure container cabin air return pipe and a first air inlet pipe pass is arranged on the side wall of the reactor cabin.

And a steam generator manhole through which the second air inlet pipe and a steam generator cabin return air pipe pass is arranged on the side wall of the steam generator cabin.

Each first air outlet pipe mouth is equidistant to be distributed, and each second air outlet pipe mouth is equidistant to be distributed.

And thermal insulation cotton material layers are laid on the manholes of the pressure vessel, the manholes of the steam generator, the top of the steam generator and the top of the reactor cabin.

The pressure vessel cabin hot air blower device and the steam generator cabin hot air blower device both comprise a hot air blower device air supply system, a hot air blower device heating system and a hot air blower device temperature control system, wherein the hot air blower device temperature control system is connected with the control end of the hot air blower device heating system, and the outlet of the hot air blower device air supply system is communicated with the inlet of the hot air blower device heating system;

an inlet of an air supply system of a hot air blower device in the pressure container cabin air heater device is communicated with a steam generator cabin return air pipe, and an outlet of a heating system of the hot air blower device in the pressure container cabin air heater device is communicated with a second air inlet pipe;

an inlet of an air supply system of a hot air blower device in the steam generator cabin air heater device is communicated with a pressure vessel cabin return air pipe, and an outlet of a heating system of the hot air blower device in the steam generator cabin air heater device is communicated with a first air inlet pipe.

The method for heating the primary loop cabin in the cold test period of the high-temperature gas cooled reactor nuclear power station comprises the following steps:

1) before a cold test of the high-temperature gas cooled reactor is started, the pressure vessel and the steam generator are in a normal pressure state, and the total heating power and the total air volume of the hot air blower device of the pressure vessel cabin and the hot air blower device of the steam generator cabin are calculated according to the ambient temperatures of metal components in the pressure vessel and the steam generator and a primary loop cabin;

2) starting a pressure vessel cabin hot air blower device and a steam generator cabin hot air blower device, respectively blowing hot air into a steam generator cabin and a reactor cabin through a first air outlet pipe nozzle and a second air outlet pipe nozzle, gradually increasing the temperature in the steam generator cabin and the reactor cabin, and maintaining the temperature in the steam generator cabin and the reactor cabin to be constant through the pressure vessel cabin hot air blower device and the steam generator cabin hot air blower device when the temperature of metal components in the pressure vessel and the steam generator meets the test requirements;

3) starting a pressure test in a primary loop cold test period, filling air into the pressure vessel and the steam generator, raising the pressure in the pressure vessel and the steam generator to the highest test pressure, and detecting the leakage rate of the primary loop and the welding seam of the pressure vessel;

4) after a loop cold test period pressure test is completed, a loop cold test pressure reduction process is started, namely, the pressure in the pressure vessel and the pressure in the steam generator are gradually reduced to the normal pressure, in the process, the temperature of metal components in the pressure vessel and the steam generator is kept constant, wherein when an emergency pressure relief abnormal working condition of welding line leakage occurs during the loop cold test pressure reduction period, the heating power and the air quantity of the pressure vessel cabin hot air blower device and the steam generator cabin hot air blower device are improved, the temperature reduction of the metal components in the pressure vessel and the steam generator is avoided, and after the loop cold test pressure reduction is finished, the pressure vessel cabin hot air blower device and the steam generator cabin hot air blower device are stopped.

The invention has the following beneficial effects:

the primary loop cabin heating system and the method thereof in the cold test period of the high-temperature gas cooled reactor nuclear power station have the advantages that when the system and the method are in specific operation, the temperature of a metal member in a reactor is raised by heating the primary loop cabin, the temperature in the primary loop cabin is ensured to be constant, the problem of primary loop cold test when the external environment temperature is lower is solved, in addition, two hot air blower devices are arranged in the system and are simultaneously heated, so that the temperature rise of the primary loop cabin space is uniformly distributed, the temperature rise rate is higher, in addition, during the actual operation, the input quantity of the first air outlet nozzle and the second air outlet nozzle can be flexibly distributed according to the requirements of wind volume and wind speed in the actual engineering heating process,

drawings

FIG. 1 is a schematic structural diagram of the present invention.

Wherein, 1 is a pressure vessel cabin hot air blower device, 2 is a pressure vessel, 3 is a hot air conduit, 4 is a steam generator, 5 is a first air inlet pipe, 61 is a first air outlet pipe nozzle, 62 is a second air outlet pipe nozzle, 7 is a pressure vessel cabin return air pipe, 8 is a steam generator cabin hot air blower device, 9 is a second air inlet pipe, 10 is a steam generator cabin return air pipe, 11 is a pressure vessel manhole, 12 is a steam generator manhole, 13 is a hot air blower device heating system, 14 is a hot air blower device temperature control system, 15 is a concrete cabin structural body, and 16 is a hot air blower device air supply system.

Detailed Description

The invention is described in further detail below with reference to the accompanying drawings:

referring to fig. 1, the primary loop cabin heating system during the cold test of the high temperature gas cooled reactor nuclear power plant according to the present invention includes a concrete cabin structural body 15, a pressure vessel 2, a steam generator 4, a first air inlet pipe 5, a pressure vessel cabin hot air blower device 1, a pressure vessel cabin return air pipe 7, a second air inlet pipe 9, a steam generator cabin hot air blower device 8, and a steam generator cabin return air pipe 10; a primary loop cabin is arranged in the concrete cabin structure body 15, the interior of the primary loop cabin is divided into a reactor cabin and a steam generator cabin, wherein the pressure vessel 2 is arranged in the reactor cabin, the steam generator 4 is arranged in the steam generator cabin, and the pressure vessel 2 is communicated with the steam generator 4 through a hot gas conduit 3; one end of a first air inlet pipe 5 is communicated with an outlet of a pressure vessel cabin air heater device 1, the other end of the first air inlet pipe 5 is inserted into a reactor cabin, a plurality of first air outlet pipe nozzles 61 are arranged on the first air inlet pipe 5, wherein each first air outlet pipe nozzle 61 is positioned in the reactor cabin and below a pressure vessel 2, one end of a pressure vessel cabin return air pipe 7 is communicated with an inlet of the pressure vessel cabin air heater device 1, and the other end of the pressure vessel cabin return air pipe 7 is inserted into the reactor cabin and above the pressure vessel 2; one end of the second air inlet pipe 9 is communicated with the outlet of the steam generator cabin air heater device 8, the other end of the second air inlet pipe 9 is inserted into the steam generator cabin, a plurality of second air outlet nozzles 62 are arranged on the second air inlet pipe 9, wherein, each second air outlet nozzle 62 is arranged in the steam generator cabin and is arranged below the steam generator 4, one end of the steam generator cabin return air pipe 10 is communicated with the inlet of the steam generator cabin air heater device 8, the other end of the steam generator cabin return air pipe 10 is inserted into the steam generator cabin and is arranged above the steam generator 4, each first air outlet nozzle 61 is distributed at equal intervals, and each second air outlet nozzle 62 is distributed at equal intervals.

A pressure vessel manhole 11 through which a pressure vessel cabin return air pipe 7 and a first air inlet pipe 5 pass is arranged on the side wall of the reactor cabin; the side wall of the steam generator chamber is provided with a steam generator manhole 12 for the second air inlet pipe 9 and the steam generator chamber return air pipe 10 to pass through.

The manholes 11 of the pressure vessel, the manholes 12 of the steam generator, the top of the steam generator 4 and the top of the reactor cabin are all laid with heat insulation cotton material layers.

The pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8 both comprise a hot air blower device air supply system 16, a hot air blower device heating system 13 and a hot air blower device temperature control system 14, wherein the hot air blower device temperature control system 14 is connected with the control end of the hot air blower device heating system 13, and the outlet of the hot air blower device air supply system 16 is communicated with the inlet of the hot air blower device heating system 13; an inlet of a hot air blower device air supply system 16 in the pressure container cabin hot air blower device 1 is communicated with a pressure container cabin return air pipe 7, and an outlet of a hot air blower device heating system 13 in the pressure container cabin hot air blower device 1 is communicated with a first air inlet pipe 5; the inlet of a hot air blower device air supply system 16 in the steam generator chamber hot air blower device 8 is communicated with a steam generator chamber return air pipe 10, and the outlet of a hot air blower device heating system 13 in the steam generator chamber hot air blower device 8 is communicated with a second air inlet pipe 9.

The method for heating the primary loop cabin in the cold test period of the high-temperature gas cooled reactor nuclear power station comprises the following steps:

1) before a cold test of the high-temperature gas cooled reactor is started, the pressure vessel 2 and the steam generator 4 are in a normal pressure state, and the total heating power and the total heating air volume of the pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8 are calculated according to the environmental temperatures of metal components in the pressure vessel 2 and the steam generator 4 and a primary loop cabin;

2) starting the pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8, respectively blowing hot air into the steam generator cabin and the reactor cabin through the first air outlet pipe nozzle 61 and the second air outlet pipe nozzle 62, gradually increasing the temperature in the steam generator cabin and the reactor cabin, and maintaining the temperature in the steam generator cabin and the reactor cabin to be constant through the pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8 when the temperature of metal components in the pressure vessel 2 and the steam generator 4 meets the test requirements;

3) starting a pressure test in a primary loop cold test period, filling air into the pressure vessel 2 and the steam generator 4, raising the pressure in the pressure vessel 2 and the steam generator 4 to the highest test pressure, and detecting the leakage rate of the primary loop and the welding seam of the pressure vessel 2, wherein in the process, the temperature of metal components in the pressure vessel 2 and the steam generator 4 is monitored in real time, and the temperature of the metal components in the pressure vessel 2 and the steam generator 4 is kept constant by dynamically adjusting the heating power and the air volume of the pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8;

4) after a loop cold test period pressure test is completed, a loop cold test pressure reduction process is started, namely, the pressure in the pressure vessel 2 and the pressure in the steam generator 4 are gradually reduced to the normal pressure, in the process, the temperature constancy of metal components in the pressure vessel 2 and the steam generator 4 is maintained, wherein, when an emergency pressure reduction abnormal working condition of welding line leakage occurs during the loop cold test pressure reduction period, the heating power and the air volume of the pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8 are improved, the temperature reduction of the metal components in the pressure vessel 2 and the steam generator 4 is avoided, and after the loop cold test pressure reduction is finished, the pressure vessel cabin hot air blower device 1 and the steam generator cabin hot air blower device 8 are stopped.

The first air outlet nozzle 61 and each second air outlet nozzle 62 are provided with an independent plug, and in actual operation, a corresponding number of first air outlet nozzles 61 and second air outlet nozzles 62 can be input according to air quantity and air speed requirements of the air outlet, and other standby first air outlet nozzles 61 and second air outlet nozzles 62 are plugged by plugs.

The air heater device heating system 13 may be composed of a heating wire or a graphene heating material.