CN206572497U - A kind of system for heating nuclear power generating sets evaporator feedwater - Google Patents

A kind of system for heating nuclear power generating sets evaporator feedwater Download PDF

Info

Publication number
CN206572497U
CN206572497U CN201720180586.3U CN201720180586U CN206572497U CN 206572497 U CN206572497 U CN 206572497U CN 201720180586 U CN201720180586 U CN 201720180586U CN 206572497 U CN206572497 U CN 206572497U
Authority
CN
China
Prior art keywords
valve group
inlet
evaporator
outlet
valve
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201720180586.3U
Other languages
Chinese (zh)
Inventor
马晓珑
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Xian Thermal Power Research Institute Co Ltd
Original Assignee
Xian Thermal Power Research Institute Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Xian Thermal Power Research Institute Co Ltd filed Critical Xian Thermal Power Research Institute Co Ltd
Priority to CN201720180586.3U priority Critical patent/CN206572497U/en
Application granted granted Critical
Publication of CN206572497U publication Critical patent/CN206572497U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Landscapes

  • Control Of Turbines (AREA)

Abstract

本实用新型一种加热核电机组蒸发器给水的系统,该系统包括高压缸、低压缸、第一至第八阀门组、旁路调节阀、蒸发器、高压加热器、凝汽器、给水泵、除氧器、低压加热器、凝结水泵。运行时,包括以下步骤:1)从汽轮机旁路调节阀前的旁路管道上连接管道通过阀门组接至高压加热器抽汽管道逆止门后的抽汽管道上;2)从汽轮机旁路调节阀前的旁路管道上连接管道通过阀门组接至除氧器抽汽管道逆止门后的抽汽管道上;3)从汽轮机旁路调节阀前的旁路管道上连接管道通过阀门组接至低压加热器抽汽管道逆止门后的抽汽管道上;4)在机组启动过程中、停机不停堆状态、汽轮机负荷大福下降工况,将旁路蒸汽引入高压加热器、除氧器、低压加热器加热蒸发器给水,减小蒸发器入口给水温度的波动,保护蒸发器运行的安全。

The utility model relates to a water supply heating system for an evaporator of a nuclear power unit. The system includes a high-pressure cylinder, a low-pressure cylinder, the first to eighth valve groups, a bypass regulating valve, an evaporator, a high-pressure heater, a condenser, a water supply pump, Deaerator, low pressure heater, condensate pump. During operation, the following steps are included: 1) connecting the pipeline from the bypass pipeline in front of the steam turbine bypass regulating valve to the steam extraction pipeline behind the check valve of the steam extraction pipeline of the high-pressure heater through the valve assembly; 2) bypassing the steam turbine The connecting pipe on the bypass pipe in front of the regulating valve is connected to the steam extraction pipe behind the check door of the deaerator extraction pipe through the valve group; 3) The connecting pipe from the bypass pipe in front of the steam turbine bypass regulating valve passes through the valve group Connected to the steam extraction pipeline behind the check door of the extraction pipeline of the low-pressure heater; 4) During the start-up process of the unit, the state of non-stop stacking when the unit is shut down, and the working condition of the steam turbine load greatly decreasing, the bypass steam is introduced into the high-pressure heater to remove oxygen The evaporator and low-pressure heater heat the feed water of the evaporator, reduce the fluctuation of the feed water temperature at the evaporator inlet, and protect the safety of the evaporator operation.

Description

一种加热核电机组蒸发器给水的系统A system for heating feed water of evaporator of nuclear power unit

技术领域:Technical field:

本实用新型属于核电技术领域,具体涉及一种加热核电机组蒸发器给水的系统。The utility model belongs to the technical field of nuclear power, and in particular relates to a system for heating water supply to evaporators of nuclear power units.

背景技术:Background technique:

高温气冷堆核电站目前是按照双堆一机来配置的。蒸发器入口给水通过低压加热器、除氧器、高压加热器来加热,满足蒸发器入口水温的要求,低压加热器、除氧器、高压加热器的正常汽源都是汽轮机的抽汽。The high-temperature gas-cooled reactor nuclear power plant is currently configured according to two reactors and one machine. The feed water at the inlet of the evaporator is heated by the low-pressure heater, deaerator and high-pressure heater to meet the water temperature requirements of the evaporator inlet. The normal steam source of the low-pressure heater, deaerator and high-pressure heater is the extraction steam of the steam turbine.

目前系统主要存在以下不足:The current system mainly has the following deficiencies:

1)在汽轮机未带负荷前,抽汽是无法取得的,蒸发器给水只能通过启动锅炉向除氧器供汽加热,启动锅炉需要长时间运行,费用高、加热效果差且不稳定;1) Before the steam turbine is under load, steam extraction cannot be obtained, and the feed water of the evaporator can only be heated by supplying steam to the deaerator through the start-up boiler. The start-up boiler needs to run for a long time, the cost is high, and the heating effect is poor and unstable;

2)机组在启动初期,大量蒸汽通过旁路排向凝汽器,排入凝汽器的蒸汽,其热量无法被利用,是能量的浪费;2) At the initial stage of unit start-up, a large amount of steam is discharged to the condenser through the bypass, and the heat of the steam discharged into the condenser cannot be used, which is a waste of energy;

3)蒸汽排入凝汽器,提高了凝结水的温度,降低了汽轮机的效率;3) The steam is discharged into the condenser, which increases the temperature of the condensed water and reduces the efficiency of the steam turbine;

4)凝结水的温度过高会影响精处理的运行;4) If the temperature of condensed water is too high, it will affect the operation of fine treatment;

5)蒸汽进入凝汽器变成凝结水后,还要利用凝结水泵打入除氧器,增加了凝结水泵的耗功;5) After the steam enters the condenser and turns into condensed water, the condensed water pump must be used to pump it into the deaerator, which increases the power consumption of the condensed water pump;

6)在停机不停堆运行工况时,汽轮机停机后,抽汽全部失去,高压加热器、低压加热器、及除氧器汽源全部失去,蒸发器入口给水温度急剧下降,影响到蒸发器的安全;6) In the non-stop stacking operation condition, after the steam turbine is shut down, all the extraction steam is lost, the high-pressure heater, low-pressure heater, and deaerator steam source are all lost, and the temperature of the feed water at the evaporator inlet drops sharply, which affects the evaporator safety;

7)在进行单堆停止工况时,汽轮机负荷减少50%,抽汽压力、流量减少,运行反应堆入口温度突然降低,影响到蒸发器的安全。7) When the single reactor is shut down, the load of the steam turbine is reduced by 50%, the extraction pressure and flow are reduced, and the inlet temperature of the operating reactor suddenly drops, which affects the safety of the evaporator.

实用新型内容:Utility model content:

本实用新型的目的在于针对目前核电机组系统的不足,提供了一种加热核电机组蒸发器给水的系统。The purpose of the utility model is to provide a system for heating the feed water of the evaporator of the nuclear power unit aiming at the deficiency of the current nuclear power unit system.

为达到上述目的,本实用新型采用如下技术方案来实现的:In order to achieve the above object, the utility model adopts the following technical solutions to realize:

一种加热核电机组蒸发器给水的系统,包括高压缸、第一阀门组、第二阀门组、第三阀门组、第四阀门组、第五阀门组、旁路调节阀、第六阀门组、第七阀门组、第八阀门组、高压加热器、凝汽器、除氧器和低压加热器;其中,A system for heating feed water to the evaporator of a nuclear power unit, including a high-pressure cylinder, a first valve group, a second valve group, a third valve group, a fourth valve group, a fifth valve group, a bypass regulating valve, a sixth valve group, The seventh valve group, the eighth valve group, high-pressure heater, condenser, deaerator and low-pressure heater; among them,

第一阀门组出口分为两股,第一股接在高压缸的入口,第二股接在旁路调节阀的入口,第二股管道称为旁路管道;在旁路管道上开三个孔,通过管道分别接在第二阀门组、第七阀门组、第八阀门组的入口;第二阀门组和第三阀门组的出口管道汇合后通过第六阀门组接在高压加热器的第二入口;第四阀门组和第七阀门组的出口管道汇合后接在除氧器的第二入口;第五阀门组和第八阀门组的出口管道汇合后接在低压加热器的第二入口。The outlet of the first valve group is divided into two strands, the first strand is connected to the inlet of the high-pressure cylinder, the second strand is connected to the inlet of the bypass regulating valve, and the second strand is called the bypass pipeline; three openings are opened on the bypass pipeline The holes are respectively connected to the inlets of the second valve group, the seventh valve group and the eighth valve group through pipelines; after the outlet pipes of the second valve group and the third valve group are merged, they are connected to the first valve group of the high pressure heater through the sixth valve group. Two inlets; the outlet pipes of the fourth valve group and the seventh valve group are connected to the second inlet of the deaerator; the outlet pipes of the fifth valve group and the eighth valve group are connected to the second inlet of the low-pressure heater .

本实用新型进一步的改进在于,包括低压缸、蒸发器、给水泵和凝结水泵;其中,The further improvement of the utility model is that it includes a low-pressure cylinder, an evaporator, a feed water pump and a condensate pump; wherein,

除氧器的出口接在给水泵的入口;给水泵的出口接在高压加热器第一入口;高压加热器的出口接在蒸发器的入口;蒸发器的出口接在第一阀门组的入口;高压缸的第一出口接在第三阀门组的入口,高压缸的第二出口接在第四阀门组的入口,高压缸的第三出口接在低压缸入口;低压缸第一出口接在第五阀门组的入口,低压缸第二出口接在凝汽器的第一入口;旁路调节阀的出口接在凝汽器的第二入口;凝汽器的出口接在凝结水泵的入口,凝结水泵的出口接在低压加热器第一入口;低压加热器的出口接在除氧器的第一入口。The outlet of the deaerator is connected to the inlet of the feed water pump; the outlet of the feed water pump is connected to the first inlet of the high pressure heater; the outlet of the high pressure heater is connected to the inlet of the evaporator; the outlet of the evaporator is connected to the inlet of the first valve group; The first outlet of the high-pressure cylinder is connected to the inlet of the third valve group, the second outlet of the high-pressure cylinder is connected to the inlet of the fourth valve group, the third outlet of the high-pressure cylinder is connected to the inlet of the low-pressure cylinder; the first outlet of the low-pressure cylinder is connected to the second The inlet of the five-valve group and the second outlet of the low-pressure cylinder are connected to the first inlet of the condenser; the outlet of the bypass regulating valve is connected to the second inlet of the condenser; the outlet of the condenser is connected to the inlet of the condensate pump. The outlet of the water pump is connected to the first inlet of the low-pressure heater; the outlet of the low-pressure heater is connected to the first inlet of the deaerator.

本实用新型进一步的改进在于,第一阀门组为蒸发器出口的截止门和调节门。The further improvement of the utility model is that the first valve group is a cut-off door and an adjustment door for the outlet of the evaporator.

本实用新型进一步的改进在于,第二阀门组、第七阀门组、第八阀门组均为截止门、调节门及逆止门。The further improvement of the utility model is that the second valve group, the seventh valve group and the eighth valve group are all cut-off doors, regulating doors and check doors.

本实用新型进一步的改进在于,第三阀门组、第四阀门组和第五阀门组均为抽汽截止门及逆止门。The further improvement of the utility model is that the third valve group, the fourth valve group and the fifth valve group are all steam extraction cut-off valves and check valves.

本实用新型进一步的改进在于,第六阀门组为截止门。The further improvement of the utility model is that the sixth valve group is a cut-off valve.

相对于现有技术,本实用新型具有如下的优点:Compared with the prior art, the utility model has the following advantages:

本实用新型一种加热核电机组蒸发器给水的系统,和目前通常使用的系统比起来有以下几方面明显的优点:The utility model is a system for heating the water supply of the evaporator of a nuclear power unit, which has the following obvious advantages compared with the currently commonly used system:

1)直接回收了部分旁路蒸汽的热量,具有节能效果;1) It directly recovers part of the heat of bypass steam, which has energy-saving effect;

2)降低了启动阶段凝结水的温度,提高了汽轮机的效率;2) Reduce the temperature of the condensed water in the start-up phase and improve the efficiency of the steam turbine;

3)降低了启动阶段凝结水的温度,对精处理系统的安全运行有利;3) Reduce the temperature of condensed water in the start-up stage, which is beneficial to the safe operation of the fine treatment system;

4)减少了凝泵的出力,具有节能效果;4) The output of the condensate pump is reduced, which has an energy-saving effect;

5)目前在启动初期,给水的温度主要靠除氧器加热,除氧器的加热汽源为启动锅炉,而启动锅炉的汽量有限,因此给水温度一般很难提高,而本实用新型引入了旁路大量汽源,通过多个环节加热给水,给水温度显著提高;5) At present, at the initial stage of start-up, the temperature of the feed water is mainly heated by the deaerator, and the heating steam source of the deaerator is the start-up boiler, and the steam volume of the start-up boiler is limited, so it is generally difficult to increase the feed water temperature, but the utility model introduces A large number of steam sources are bypassed, the feed water is heated through multiple links, and the temperature of the feed water is significantly increased;

7)在汽轮机跳闸,汽轮机抽汽丧失后,旁路投入运行后,低压加热器、除氧器、高压加热器汽源切换到旁路蒸汽,蒸发器入口温度不会发生剧烈波动,提高了机组运行的安全性。7) After the steam turbine trips, the steam extraction of the steam turbine is lost, and the bypass is put into operation, the steam source of the low-pressure heater, deaerator, and high-pressure heater is switched to the bypass steam, and the temperature at the inlet of the evaporator will not fluctuate violently, which improves the performance of the unit. security of operation.

8)在单堆跳闸等引起汽轮机负荷大幅下降的工况,旁路投入运行后,低压加热器、除氧器、高压加热器汽源切换到旁路蒸汽,蒸发器入口温度不会发生剧烈波动,提高了机组运行的安全性。8) In the working condition where the load of the steam turbine drops sharply due to tripping of a single pile, after the bypass is put into operation, the steam source of the low-pressure heater, deaerator and high-pressure heater is switched to the bypass steam, and the inlet temperature of the evaporator will not fluctuate violently , improving the safety of unit operation.

附图说明:Description of drawings:

图1为一种加热核电机组蒸发器给水的系统的结构框图。Fig. 1 is a structural block diagram of a system for heating feed water to an evaporator of a nuclear power unit.

图中:1-高压缸,2-低压缸,3-第一阀门组,4-第二阀门组,5-第三阀门组,6-第四阀门组,7-第五阀门组,8-旁路调节阀,9-蒸发器,10-第六阀门组,11-第七阀门组,12-第八阀门组,13-高压加热器,14-凝汽器,15-给水泵,16-除氧器,17-低压加热器,18-凝结水泵。In the figure: 1-high pressure cylinder, 2-low pressure cylinder, 3-first valve group, 4-second valve group, 5-third valve group, 6-fourth valve group, 7-fifth valve group, 8- Bypass regulating valve, 9-evaporator, 10-sixth valve group, 11-seventh valve group, 12-eighth valve group, 13-high pressure heater, 14-condenser, 15-feed water pump, 16- Deaerator, 17-low pressure heater, 18-condensate pump.

具体实施方式:detailed description:

以下结合附图对本实用新型做出进一步的详细说明。Below in conjunction with accompanying drawing, the utility model is further described in detail.

如图1所示,本实用新型提供的一种加热核电机组蒸发器给水的系统,包括高压缸1、低压缸2、第一阀门组3、第二阀门组4、第三阀门组5、第四阀门组6、第五阀门组7、旁路调节阀8、蒸发器9、第六阀门组10、第七阀门组11、第八阀门组12、高压加热器13、凝汽器14、给水泵15、除氧器16、低压加热器17和凝结水泵18;其中,除氧器16的出口接在给水泵15的入口;给水泵15的出口接在高压加热器13第一入口;高压加热器13的出口接在蒸发器9的入口;蒸发器9的出口接在第一阀门组3的入口;第一阀门组3出口分为两股,第一股接在高压缸1的入口,第二股接在旁路调节阀8的入口,第二股管道称为旁路管道;在旁路管道上开三个孔,通过管道分别接在第二阀门组4、第七阀门组11、第八阀门组12的入口;第二阀门组4和第三阀门组5的出口管道汇合后通过第六阀门组10接在高压加热器13的第二入口;第四阀门组6和第七阀门组11的出口管道汇合后接在除氧器16的第二入口;第五阀门组7和第八阀门组12的出口管道汇合后接在低压加热器17的第二入口;高压缸1的第一出口接在第三阀门组5的入口,高压缸1的第二出口接在第四阀门组6的入口,高压缸1的第三出口接在低压缸2入口;低压缸2第一出口接在第五阀门组7的入口,低压缸2第二出口接在凝汽器14的第一入口;旁路调节阀8的出口接在凝汽器14的第二入口;凝汽器14的出口接在凝结水泵18的入口,凝结水泵18的出口接在低压加热器17第一入口;低压加热器17的出口接在除氧器16的第一入口。As shown in Figure 1, the utility model provides a system for heating the water supply of the evaporator of a nuclear power unit, including a high-pressure cylinder 1, a low-pressure cylinder 2, a first valve group 3, a second valve group 4, a third valve group 5, a Four valve group 6, fifth valve group 7, bypass regulating valve 8, evaporator 9, sixth valve group 10, seventh valve group 11, eighth valve group 12, high pressure heater 13, condenser 14, supply Water pump 15, deaerator 16, low-pressure heater 17 and condensate pump 18; wherein, the outlet of deaerator 16 is connected to the inlet of feedwater pump 15; the outlet of feedwater pump 15 is connected to the first inlet of high-pressure heater 13; high-pressure heating The outlet of the device 13 is connected to the inlet of the evaporator 9; the outlet of the evaporator 9 is connected to the inlet of the first valve group 3; the outlet of the first valve group 3 is divided into two strands, the first strand is connected to the inlet of the high-pressure cylinder 1, the second The two strands are connected to the inlet of the bypass regulating valve 8, and the second pipeline is called the bypass pipeline; three holes are opened on the bypass pipeline, and the pipelines are respectively connected to the second valve group 4, the seventh valve group 11, the The inlet of the eight-valve group 12; the outlet pipes of the second valve group 4 and the third valve group 5 are connected to the second inlet of the high-pressure heater 13 through the sixth valve group 10; the fourth valve group 6 and the seventh valve group 11 outlet pipes are connected to the second inlet of the deaerator 16; the outlet pipes of the fifth valve group 7 and the eighth valve group 12 are connected to the second inlet of the low-pressure heater 17; The outlet is connected to the inlet of the third valve group 5, the second outlet of the high-pressure cylinder 1 is connected to the inlet of the fourth valve group 6, the third outlet of the high-pressure cylinder 1 is connected to the inlet of the low-pressure cylinder 2; the first outlet of the low-pressure cylinder 2 is connected to the The inlet of the fifth valve group 7 and the second outlet of the low-pressure cylinder 2 are connected to the first inlet of the condenser 14; the outlet of the bypass regulating valve 8 is connected to the second inlet of the condenser 14; the outlet of the condenser 14 is connected to At the inlet of the condensate pump 18, the outlet of the condensate pump 18 is connected to the first inlet of the low-pressure heater 17; the outlet of the low-pressure heater 17 is connected to the first inlet of the deaerator 16.

所述第一阀门组3为蒸发器9出口的截止门和调节门。The first valve group 3 is a cut-off valve and a regulating valve for the outlet of the evaporator 9 .

所述第二阀门组4、第七阀门组11和第八阀门组12均为截止门、调节门及逆止门。The second valve group 4 , the seventh valve group 11 and the eighth valve group 12 are cut-off valves, regulating valves and check valves.

所述第三阀门组5、第四阀门组6和第五阀门组7均为抽汽截止门及逆止门。The third valve group 5 , the fourth valve group 6 and the fifth valve group 7 are steam extraction cut-off valves and check valves.

所述第六阀门组10为截止门。The sixth valve group 10 is a cut-off valve.

为了对本实用新型进一步的了解,现对其运行过程做出如下说明:In order to further understand the utility model, its operating process is now described as follows:

1)在反应堆启动后,汽轮机冲转前,蒸发器9所产生的蒸汽通过旁路调节阀8排入凝汽器;1) After the reactor is started and before the steam turbine runs, the steam generated by the evaporator 9 is discharged into the condenser through the bypass regulating valve 8;

2)打开第九阀门组12中的截止阀,通过第九阀门组12的调节阀,控制蒸汽进入低压加热器17,投入低压加热器17加热蒸发器入口给水;2) Open the shut-off valve in the ninth valve group 12, control the steam to enter the low-pressure heater 17 through the regulating valve of the ninth valve group 12, and drop into the low-pressure heater 17 to heat the inlet feed water of the evaporator;

3)打开第八阀门组11中的截止阀,通过第八阀门组11的调节阀,控制蒸汽进入除氧器16,投入除氧器16加热蒸发器入口给水;3) Open the shut-off valve in the eighth valve group 11, control the steam to enter the deaerator 16 through the regulating valve of the eighth valve group 11, and drop into the deaerator 16 to heat the evaporator inlet feed water;

4)打开第三阀门组5、第七阀门组10中的截止阀,通过第三阀门组5的调节阀,控制蒸汽进入高压加热器13,投入高压加热器13加热蒸发器入口给水;4) Open the cut-off valves in the third valve group 5 and the seventh valve group 10, control the steam to enter the high-pressure heater 13 through the regulating valve of the third valve group 5, and put into the high-pressure heater 13 to heat the evaporator inlet water supply;

5)在汽轮机冲转带负荷后,随着汽轮机负荷的增大,旁路蒸汽的减少,当汽轮机抽汽量满足蒸发器给水加热要求后,低压加热器17、除氧器16、高压加热器13的汽源切换为抽汽,利用抽汽加热蒸发器给水;5) After the steam turbine runs with load, as the steam turbine load increases, the bypass steam decreases. When the steam extraction volume of the steam turbine meets the heating requirements of the evaporator feed water, the low-pressure heater 17, the deaerator 16, and the high-pressure heater The steam source of 13 is switched to extraction steam, and the evaporator feed water is heated by extraction steam;

6)在跳机不跳堆工况,汽轮机跳机抽汽汽源切断,旁路投入运行后,低压加热器17、除氧器16、高压加热器13的汽源切换为旁路蒸汽,利用旁路蒸汽加热蒸发器给水,避免蒸发器入口汽温发生大幅度降低,保护蒸发器安全;6) In the condition of tripping and non-stacking, the steam source of the steam turbine tripping is cut off, and after the bypass is put into operation, the steam sources of the low-pressure heater 17, deaerator 16, and high-pressure heater 13 are switched to bypass steam, and the steam is used Bypass steam heats the feed water of the evaporator, avoiding a significant drop in the steam temperature at the inlet of the evaporator, and protecting the safety of the evaporator;

7)在汽轮机负荷减小抽汽压力不足,低压加热器17、除氧器16、高压加热器13的汽源切换为旁路蒸汽,利用旁路蒸汽加热蒸发器给水,避免蒸发器入口汽温发生大幅度波动,保护蒸发器安全;7) When the steam turbine load decreases and the extraction pressure is insufficient, the steam source of the low-pressure heater 17, deaerator 16, and high-pressure heater 13 is switched to bypass steam, and the bypass steam is used to heat the feed water of the evaporator to avoid the steam temperature at the inlet of the evaporator. Large fluctuations occur to protect the safety of the evaporator;

8)在双堆一机的核电机组中,一台反应堆跳堆,另一台反应堆正常运行,汽轮机负荷降低到50%负荷以下,汽轮机抽汽压力降低,抽汽量减少,使得运行蒸发器入口温度降低,影响到蒸发器安全。此时可以投入旁路,利用旁路蒸汽给低压加热器17、除氧器16、高压加热器13供汽,保证蒸发器入口给水温度。8) In a nuclear power unit with two reactors and one machine, one reactor jumps and the other reactor operates normally, the load of the steam turbine is reduced to below 50% load, the steam extraction pressure of the steam turbine is reduced, and the steam extraction volume is reduced, so that the inlet of the operating evaporator The temperature drops, which affects the safety of the evaporator. At this time, the bypass can be put into use, and the bypass steam can be used to supply steam to the low-pressure heater 17, the deaerator 16, and the high-pressure heater 13, so as to ensure the feedwater temperature at the evaporator inlet.

Claims (6)

1.一种加热核电机组蒸发器给水的系统,其特征在于,包括高压缸(1)、第一阀门组(3)、第二阀门组(4)、第三阀门组(5)、第四阀门组(6)、第五阀门组(7)、旁路调节阀(8)、第六阀门组(10)、第七阀门组(11)、第八阀门组(12)、高压加热器(13)、凝汽器(14)、除氧器(16)和低压加热器(17);其中,1. A system for heating nuclear power unit evaporator feed water, characterized in that it comprises a high-pressure cylinder (1), a first valve group (3), a second valve group (4), a third valve group (5), a fourth Valve group (6), fifth valve group (7), bypass regulating valve (8), sixth valve group (10), seventh valve group (11), eighth valve group (12), high pressure heater ( 13), condenser (14), deaerator (16) and low pressure heater (17); wherein, 第一阀门组(3)出口分为两股,第一股接在高压缸(1)的入口,第二股接在旁路调节阀(8)的入口,第二股管道称为旁路管道;在旁路管道上开三个孔,通过管道分别接在第二阀门组(4)、第七阀门组(11)、第八阀门组(12)的入口;第二阀门组(4)和第三阀门组(5)的出口管道汇合后通过第六阀门组(10)接在高压加热器(13)的第二入口;第四阀门组(6)和第七阀门组(11)的出口管道汇合后接在除氧器(16)的第二入口;第五阀门组(7)和第八阀门组(12)的出口管道汇合后接在低压加热器(17)的第二入口。The outlet of the first valve group (3) is divided into two strands, the first strand is connected to the inlet of the high-pressure cylinder (1), the second strand is connected to the inlet of the bypass regulating valve (8), and the second strand is called the bypass pipeline Three holes are opened on the bypass pipeline, and the inlets of the second valve group (4), the seventh valve group (11), and the eighth valve group (12) are respectively connected to by the pipeline; the second valve group (4) and The outlet pipes of the third valve group (5) are connected to the second inlet of the high-pressure heater (13) by the sixth valve group (10) after they merge; the outlets of the fourth valve group (6) and the seventh valve group (11) The second inlet of the deaerator (16) is connected after the pipeline is merged; the outlet pipeline of the fifth valve group (7) and the eighth valve group (12) is connected after the second inlet of the low pressure heater (17). 2.根据权利要求1所述的一种加热核电机组蒸发器给水的系统,其特征在于,包括低压缸(2)、蒸发器(9)、给水泵(15)和凝结水泵(18);其中,2. A system for heating nuclear power unit evaporator feedwater according to claim 1, characterized in that it comprises a low-pressure cylinder (2), an evaporator (9), a feedwater pump (15) and a condensate pump (18); wherein , 除氧器(16)的出口接在给水泵(15)的入口;给水泵(15)的出口接在高压加热器(13)第一入口;高压加热器(13)的出口接在蒸发器(9)的入口;蒸发器(9)的出口接在第一阀门组(3)的入口;高压缸(1)的第一出口接在第三阀门组(5)的入口,高压缸(1)的第二出口接在第四阀门组(6)的入口,高压缸(1)的第三出口接在低压缸(2)入口;低压缸(2)第一出口接在第五阀门组(7)的入口,低压缸(2)第二出口接在凝汽器(14)的第一入口;旁路调节阀(8)的出口接在凝汽器(14)的第二入口;凝汽器(14)的出口接在凝结水泵(18)的入口,凝结水泵(18)的出口接在低压加热器(17)第一入口;低压加热器(17)的出口接在除氧器(16)的第一入口。The outlet of the deaerator (16) is connected to the inlet of the feedwater pump (15); the outlet of the feedwater pump (15) is connected to the first inlet of the high pressure heater (13); the outlet of the high pressure heater (13) is connected to the evaporator ( 9) inlet; the outlet of the evaporator (9) is connected to the inlet of the first valve group (3); the first outlet of the high-pressure cylinder (1) is connected to the inlet of the third valve group (5), and the high-pressure cylinder (1) The second outlet of the cylinder is connected to the entrance of the fourth valve group (6), the third outlet of the high-pressure cylinder (1) is connected to the inlet of the low-pressure cylinder (2); the first outlet of the low-pressure cylinder (2) is connected to the fifth valve group (7) ), the second outlet of the low-pressure cylinder (2) is connected to the first inlet of the condenser (14); the outlet of the bypass regulating valve (8) is connected to the second inlet of the condenser (14); the condenser The outlet of (14) is connected to the inlet of the condensate pump (18), and the outlet of the condensate pump (18) is connected to the first inlet of the low-pressure heater (17); the outlet of the low-pressure heater (17) is connected to the deaerator (16) the first entrance. 3.根据权利要求1所述的一种加热核电机组蒸发器给水的系统,其特征在于,第一阀门组(3)为蒸发器(9)出口的截止门和调节门。3. A system for heating nuclear power unit evaporator feed water according to claim 1, characterized in that the first valve group (3) is a cut-off gate and an adjustment gate for the outlet of the evaporator (9). 4.根据权利要求1所述的一种加热核电机组蒸发器给水的系统,其特征在于,第二阀门组(4)、第七阀门组(11)、第八阀门组(12)均为截止门、调节门及逆止门。4. A system for heating nuclear power unit evaporator feed water according to claim 1, characterized in that, the second valve group (4), the seventh valve group (11), and the eighth valve group (12) are all cut-off Doors, adjustable doors and check doors. 5.根据权利要求1所述的一种加热核电机组蒸发器给水的系统,其特征在于,第三阀门组(5)、第四阀门组(6)和第五阀门组(7)均为抽汽截止门及逆止门。5. A system for heating nuclear power unit evaporator feedwater according to claim 1, characterized in that the third valve group (5), the fourth valve group (6) and the fifth valve group (7) are pumping Steam cut-off door and check door. 6.根据权利要求1所述的一种加热核电机组蒸发器给水的系统,其特征在于,第六阀门组(10)为截止门。6 . The system for heating feed water to an evaporator of a nuclear power unit according to claim 1 , wherein the sixth valve group ( 10 ) is a cut-off valve. 7 .
CN201720180586.3U 2017-02-27 2017-02-27 A kind of system for heating nuclear power generating sets evaporator feedwater Active CN206572497U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201720180586.3U CN206572497U (en) 2017-02-27 2017-02-27 A kind of system for heating nuclear power generating sets evaporator feedwater

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201720180586.3U CN206572497U (en) 2017-02-27 2017-02-27 A kind of system for heating nuclear power generating sets evaporator feedwater

Publications (1)

Publication Number Publication Date
CN206572497U true CN206572497U (en) 2017-10-20

Family

ID=60059306

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201720180586.3U Active CN206572497U (en) 2017-02-27 2017-02-27 A kind of system for heating nuclear power generating sets evaporator feedwater

Country Status (1)

Country Link
CN (1) CN206572497U (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106678770A (en) * 2017-02-27 2017-05-17 西安热工研究院有限公司 System and method for heating feed water of evaporator of nuclear power unit

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106678770A (en) * 2017-02-27 2017-05-17 西安热工研究院有限公司 System and method for heating feed water of evaporator of nuclear power unit
CN106678770B (en) * 2017-02-27 2023-05-30 西安热工研究院有限公司 A system and method for heating nuclear power unit evaporator feed water

Similar Documents

Publication Publication Date Title
CN106678770A (en) System and method for heating feed water of evaporator of nuclear power unit
CN105605551B (en) A kind of system and method for utilization turbine by-pass steam heating pot stove feedwater
CN102787870B (en) Method for improving primary frequency modulation capacity of heat supply unit
CN110131003B (en) A system and method for starting and stopping the secondary circuit of a high temperature gas-cooled reactor nuclear power unit
CN111577410B (en) Gas turbine inlet air temperature control device and gas turbine inlet air temperature control method
CN102588938A (en) Energy-saving quick power regulating system of thermal generator set and method
CN106194297A (en) The double branch road heating system of a kind of cogeneration turbine
CN210118175U (en) Pressurized water reactor nuclear power unit two-loop thermodynamic system self-adaptation steam supply system
CN203605211U (en) Water feeding system of boiler
CN205447710U (en) System for utilize steam turbine bypass steam heating boiler feed water
CN210858830U (en) A deep thermal and electrolytic coupling system of ejector gas distribution based on axial thrust balance
CN105156160A (en) Through-flow parameter optimization effect improvement and peak regulation system for main compound turbine of front machine
CN112303610A (en) Operation system and method for recovering high-energy water in shutdown and non-shutdown operation mode
CN108167036A (en) A kind of system and method for nuclear power generating sets vapor self
CN107120713B (en) High back pressure heat supply unit condensate water prevents super temperature cooling system
CN112856363A (en) System and method for improving heat supply steam parameters of deep peak shaving heat supply unit
CN204552846U (en) A kind of back pressure steam turbines utilization system
CN202452469U (en) Power quick-adjusting device for novel thermal generator set
CN210088818U (en) System for nuclear power starts electric boiler heat reserve
CN207776920U (en) A kind of system of nuclear power generating sets vapor self
CN110726168A (en) A system for maximizing the utilization of waste heat of steam turbines in thermal power plants
CN114991892A (en) Deep peak regulation steam turbine system and operation method
CN114991893A (en) Front-mounted steam turbine system for deep peak shaving and operation method
CN103628937A (en) Method for better utilizing waste gas of turboset
CN110118346A (en) System and method for nuclear power starting electric boiler hot standby

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant