CN109799142A - Nuclear power station water pressure test loop heating system and circular heating method - Google Patents
Nuclear power station water pressure test loop heating system and circular heating method Download PDFInfo
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- CN109799142A CN109799142A CN201811565207.8A CN201811565207A CN109799142A CN 109799142 A CN109799142 A CN 109799142A CN 201811565207 A CN201811565207 A CN 201811565207A CN 109799142 A CN109799142 A CN 109799142A
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Abstract
The present invention relates to a kind of nuclear power station water pressure test loop heating system and circular heating method, loop heating system includes heater and water inlet circuit, goes out water loop.Water inlet circuit is connect with heater, and the water for heating heater is transported in steam generator.Water loop is connect with heater out, for the water in steam generator to be discharged to heater.Heater, steam generator, goes out water loop one closed loop cycle of formation at water inlet circuit, persistently steam generator can be heated, heat makes full use of, heating efficiency is high, required short time limit, achieve the effect that steam generator tube sheet is quickly heated to desired temperature, improves the quality and safety management level of project；After heating efficiency improves, the reduction of heating system electrical power can be made, upstream power load is small, and device redundancy is higher.
Description
Technical field
The present invention relates to nuclear power fields, more specifically to a kind of nuclear power station water pressure test loop heating system and follow
Ring heating means.
Background technique
Evaporator secondary side water pressure test project in nuclear plant major overhaul in the related technology is suitable for labour front evaporator
The device water pressure test and the in-service evaporator water pressure test can also be applied to the water pressure test system for needing to heat.
Original technology is tried using draining heating evaporation device mode is filled repeatedly with any one steam generator secondary side hydraulic pressure
For testing, test process is filled row's heating method and is briefly discussed below:
Heating water tank is from auxiliary feedwater water tank intake, and starting heater 45min heats water by 50 DEG C after water tank is filled
To 90 DEG C, tank hot water is filled with steam generator heating tube sheet and cylinder by extra feed valve by starting charging pump 5min, in advance
After hot 35min or so, starting temporary drainage pump 15min by water exhaust.It repeatedly will after 24 starting heaters, water-filling and drainings
Metal temperature be heated to 43 DEG C of test requirements document temperature or more, normal time-consuming about 20H.
The shortcoming of former scheme:
1) original technology scheme using draining heating evaporation device is filled repeatedly, and thermal loss is big, and heating efficiency is low, the required duration
It is long；
2) original technology scheme needs the power of heater larger, and upstream power load and equipment cost are higher；
3) original technology scheme needs personnel to cooperate heating water tank and evaporator water-filling and drainage works, human cost for a long time
It is high.
Summary of the invention
The technical problem to be solved in the present invention is that provide a kind of nuclear power station water pressure test loop heating system and circulation plus
Hot method.
The technical solution adopted by the present invention to solve the technical problems is: constructing a kind of nuclear power station water pressure test circulating-heating
System, including heater and water inlet circuit, water loop out；
The water inlet circuit is connect with the heater, and the water for heating the heater is transported to steam generator
It is interior；
The water loop out is connect with the heater, for the water in the steam generator to be discharged to the heating
Device.
Preferably, the charging pump that the water inlet branch includes water inlet pipe and is arranged on the water inlet pipe, the water outlet branch
Road includes outlet pipe and the back water pump that is arranged on the outlet pipe.
Preferably, it is additionally provided on the water inlet pipe into water manual modulation valve, check valve, hand stop valve, the water inlet hand
Dynamic regulating valve is arranged in parallel with the charging pump；
Water outlet manual modulation valve is additionally provided on the outlet pipe, the water outlet manual modulation valve is in parallel with the back water pump to be set
It sets.
Preferably, the part that the water inlet pipe is located at the charging pump and heater is equipped with for the water inlet pipe moisturizing
Moisturizing interface and the small pump that is connect with the moisturizing interface.
Preferably, the heater includes cabinet, to the heating device of the case intracorporal water heating.
Preferably, the inside middle and lower part of the cabinet is arranged in the heating device, and the heating device includes heating rod.
Preferably, the heater further include temperature transmitter for measuring the temperature of the intracorporal water of the case and
For measuring the liquid level detection device of the intracorporal water level of the case.
Preferably, the nuclear power station water pressure test loop heating system further include water tank and be connected to the water tank and
Water-supply-pipe between the heater, the water-supply-pipe are equipped with control valve and water delivery filter.
Preferably, the nuclear power station water pressure test loop heating system further includes for controlling the heater, intaking back
Road, the control system for going out water loop, the nuclear power station water pressure test loop heating system further include for monitoring the steam hair
The temperature detection part of the temperature of raw device, to stop heating after the steam generator reaches requirement temperature.One kind is based on institute
State the circular heating method of nuclear power station water pressure test loop heating system, comprising the following steps:
S1, the heater heat water；
The water that S2, the heater heat is transported in steam generator through the water inlet circuit, to the steam generation
Device heating；
Water in S3, the steam generator is discharged to the heater, return step S1 circulation through the water loop out
Step S1 to S3.
Preferably, water inlet branch road is equipped with moisturizing interface for moisturizing, the circular heating method further include with
Lower step:
After the water temperature in the loop heating system reaches target temperature, the moisturizing interface, Xiang Suoshu steam are opened
Moisturizing in generator reduces the water temperature in the loop heating system to lower limit temperature, and continues cycling through step S1 to S3, until institute
It states after steam generator reaches requirement temperature, the heater stops heating.
Implement nuclear power station water pressure test loop heating system and circular heating method of the invention, has below beneficial to effect
Fruit: heater, steam generator, goes out water loop one closed loop cycle of formation at water inlet circuit, can persistently add to steam generator
Heat, heat make full use of, and heating efficiency is high, required short time limit, reach and steam generator tube sheet is quickly heated to desired temperature
The effect of degree improves the quality and safety management level of project；After heating efficiency improves, heating system electrical power can be made to drop
Low, upstream power load is small, and device redundancy is higher.
Loop heating system can monitor water temperature in circulation loop in real time, automatic to be followed when water temperature reaches target temperature
Loop back path moisturizing realizes that circulating backwater rate increases to accelerate the mesh of heat transmitting with the water level of steam generator in increase system
, while Auto-matching heater power is to control water temperature within target temperature.
Detailed description of the invention
Present invention will be further explained below with reference to the attached drawings and examples, in attached drawing:
Fig. 1 is the system schematic of the nuclear power station water pressure test loop heating system in the embodiment of the present invention；
Fig. 2 is the schematic illustration of the nuclear power station water pressure test loop heating system in the embodiment of the present invention.
Specific embodiment
For a clearer understanding of the technical characteristics, objects and effects of the present invention, now control attached drawing is described in detail
A specific embodiment of the invention.
As shown in Figure 1 and Figure 2, the nuclear power station water pressure test loop heating system in a preferred embodiment of the invention includes
Heater 1 and water inlet circuit 3 go out water loop 4.
Water inlet circuit 3 is connect with heater 1, and the water for heating heater 1 is transported in steam generator 2.Water outlet
Circuit 4 is connect with heater 1, for the water in steam generator 2 to be discharged to heater 1.
Heater 1, steam generator 2, goes out one closed loop cycle of formation of water loop 4 at water inlet circuit 3, can be persistently to steam
Generator 2 heats, and gives sealing and circulating moisturizing when water temperature is close to 90 DEG C, and heat makes full use of, and heating efficiency is high, required short time limit,
Achieve the effect that 2 tube sheet of steam generator is quickly heated to desired temperature, improves the quality and safety management level of project.
After heating efficiency improves, the reduction of heating system electrical power can be made, only 600KW or lower power designs, that is, alternative previous
750KW heater 1, upstream power load is small, and device redundancy is higher.
In the present embodiment, steam generator 2 includes two steam generators 2.Water inlet circuit 3 includes two water inlet branches
31, with heater 1 and wherein, a steam generator 2 is connect each water inlet branch 31, and water inlet branch 31 is equipped with moisturizing circuit, can
To the moisturizing of sealing and circulating circuit.Water loop 4 includes two water outlet branches 41 out, and each water outlet branch 41 is with heater 1 and wherein
The connection of one steam generator 2.
Loop heating system can be applied in the evaporator secondary side water pressure test project of nuclear power station, by being accordingly
System Interface design, can meet nuclear power demand, be able to achieve 2 steam generators 2 simultaneously or intersection is evaporated the heating of device secondary side.
The quantity of steam generator 2 can be one, a heating system can also can be allowed to the steam of different number to be multiple
Generator 2 is heated, and water inlet branch 31, the quantity for being discharged branch 41 are corresponded with steam generator 2 respectively.
In general, the position that water inlet circuit 3 is connect with steam generator 2 is higher than what water loop 4 was connect with steam generator 2
Position.Preferably, the position that connect with steam generator 2 of water inlet circuit 3 is located at the upper end of steam generator 2, out water loop 4 and
The position that steam generator 2 connects is located at the lower end of steam generator 2, and water is allowed from top to bottom to flow in steam generator 2, protects
Card heats each position equilibrium of steam generator 2, and the energy of water is also allowed to be entirely delivered to steam generator 2.
The lower end of steam generator 2 is additionally provided with the fluid level transmitter 21 being connected to 2 inner cavity of steam generator, can measure steaming
The liquid level of liquid in vapour generator 2.
Water inlet branch 31 includes water inlet pipe 311 and the charging pump 312 being arranged on water inlet pipe 311, further, water inlet pipe
It is additionally provided on 311 into water manual modulation valve 313, check valve 314, feed water flow meter 315, electrical ball valve 316, hand stop valve
317 equal control units, can control flow, flow velocity and flow direction.Preferably, water inlet manual modulation valve 313 is in parallel with charging pump 312
Setting, can manually control flow.
Water outlet branch 41 includes outlet pipe 411 and the back water pump 412 being arranged on outlet pipe 411, further, outlet pipe
It is additionally provided with water outlet manual modulation valve 413 on 411, goes out water filter 414, water flow meter 415, manual ball valve 416, can control
Flow, flow velocity.Preferably, water outlet manual modulation valve 413 is arranged in parallel with back water pump 412, can manually control flow.
Moisturizing circuit includes being located at the part setting of charging pump 312 and heater 1, for water inlet pipe in water inlet pipe 311
The moisturizing interface 318 of 311 moisturizings and the small pump 319 connecting with moisturizing interface 318, small pump 319 are connect with water tank 5, can be
During water flowing in circulation loop, the moisturizing into circulation loop.
Heater 1 includes cabinet 11, to the heating device 12 of the water heating in cabinet 11.Heating device 12 is arranged in cabinet
11 inside sidewalls middle and lower part, heating device 12 include heating rod, and heating device 12 is sealed in cabinet 11 by flange form connection
In, in other embodiments, heating device 12 may also comprise heater strip, heating plate etc..
Further, heater 1 further includes temperature transmitter 13, the Yi Jiyong for measuring the temperature of the water in cabinet 11
In the liquid level detection device 14 of the water level in measurement cabinet 11.
Temperature transmitter 13 is arranged on the side wall of cabinet 11, can measure temperature, and the temperature of the water allowed in cabinet 11 reaches
To predetermined value.
Liquid level detection device 14 includes the liquid level sensor 141 being arranged in cabinet 11 and is arranged outside cabinet 11 simultaneously
The liquidometer 142 being connected to in cabinet 11.Liquid level sensor 141 can obtain liquid level signal according to liquid level, and liquidometer 142 can
Directly the liquid level in cabinet 11 is arrived in range estimation.
The water delivery that nuclear power station water pressure test loop heating system further includes water tank 5, is connected between water tank 5 and heater 1
Pipe 6, and for controlling heater 1, water inlet circuit 3, the control system 7 for going out water loop 4, nuclear power station water pressure test circulating-heating
System further includes the temperature detection part for monitoring the temperature of steam generator 2, temperature detection part and 7 communication link of control system
It connects.
Temperature detection part is usually temp probe, is measured the metal temperature of steam generator 2, so as in steam generator
2 reach stopping heating after requirement temperature, and it is usually 43 DEG C that the heating of steam generator 2, which to be achieved need to require temperature,.
Heater 1, water inlet circuit 3, steam generator 2, water loop 4 forms closed circulation loop, nuclear power station hydraulic pressure out
The circular heating method of test cycle heating system, comprising the following steps:
S1, heater 1 heat water；
The water that S2, heater 1 heat is transported in steam generator 2 through water inlet circuit 3, is heated to steam generator 2；
Water in S3, steam generator 2 is discharged to heater 1 through going out water loop 4, and return step S1 circulation step S1 is extremely
S3。
Circular heating method is further comprising the steps of:
After water temperature in loop heating system reaches target temperature, moisturizing interface is opened, is mended into steam generator 2
Water reduces the water temperature in loop heating system to lower limit temperature, and continues cycling through step S1 to S3, until steam generator 2 reaches
It is required that heater 1 stops heating after temperature.
Preferably, water inlet branch 31 is equipped with temperature detector, measures the water temperature in circulation loop.Target temperature is 88-
90 DEG C, can also be 85-90 DEG C of other equal high temperature ranges.
After water temperature in loop heating system reaches target temperature, moisturizing interface 318 is opened, in the work of charging pump 312
With the lower moisturizing into steam generator 2, the water temperature in loop heating system can be reduced, the lower limit temperature after usually reducing is 80
℃。
Moisturizing reduces the water temperature in circuit after reaching target temperature, can be too high to avoid the temperature of the water in circulation loop
After vaporize, cause the water flow in circuit to lose, influence flowing and heat transmitting.Meanwhile it can also be automatic by the way of moisturizing heating
Power with heater 1, to control water temperature within target temperature.
After water temperature in loop heating system is reduced to lower limit temperature, heater 1 can continue to add in the water in circulation loop
Heat, continuous heating steam generator 2.After circular water replenishing, the water level of steam generator 2 can be promoted, in 2 water of steam generator
Circulating backwater rate is improved after the pressure head increase of position, the amount of flowing water also increases in circulation loop, promotes the heat of carrying, in turn
Accelerate heat transmitting.
Water-supply-pipe 6 is equipped with control valve 61 and water delivery filter 62, and water tank 5 can inject water into heater 1 at the beginning,
Later period can the moisturizing into heater 1 in the case where water loss.
In conjunction with each control valve 61 in control system 7 and circuit, pipeline, automatically and manually two kinds of circulating-heatings may be implemented
The long-range Control experiment process of mode, improves level of security, reduces human cost.
Using present techniques advantage and have the beneficial effect that:
1) lifting test ability: automatically and manually circulating-heating mode, which is compared, fills row's heating method intelligence degree height；
2) it reduces time cost: saving project duration 10H or more；
3) it reduces human cost: saving 2 people of project team member or more；
4) improve level of security: the design super liquid level safeguard measure of over-temp and over-pressure, user experience are more safe and reliable；
5) raise the management level: the Standardization Practice for promoting evaporator secondary side water pressure test project is horizontal.
It is to be appreciated that above-mentioned each technical characteristic can be used in any combination and unrestricted.
The above description is only an embodiment of the present invention, is not intended to limit the scope of the invention, all to utilize this hair
Equivalent structure or equivalent flow shift made by bright specification and accompanying drawing content is applied directly or indirectly in other relevant skills
Art field, is included within the scope of the present invention.
Claims (10)
1. a kind of nuclear power station water pressure test loop heating system, which is characterized in that including heater (1) and water inlet circuit
(3), go out water loop (4)；
The water inlet circuit (3) connect with the heater (1), for the water that the heater (1) is heated to be transported to steam
In generator (2)；
Water loop (4) out are connect with the heater (1), for the water in the steam generator (2) to be discharged to institute
State heater (1).
2. nuclear power station water pressure test loop heating system according to claim 1, which is characterized in that the water inlet branch
(31) charging pump (312) for including water inlet pipe (311) and being arranged on the water inlet pipe (311), water outlet branch (41) packet
The back water pump (412) for including water pipe (411) and being arranged on the outlet pipe (411).
3. nuclear power station water pressure test loop heating system according to claim 2, which is characterized in that the water inlet pipe
(311) it is additionally provided on into water manual modulation valve (313), check valve (314), hand stop valve (317), the water inlet manually adjusts
Valve (313) is arranged in parallel with the charging pump (312)；
Be additionally provided on the outlet pipe (411) water outlet manual modulation valve (413), the water outlet manual modulation valve (413) with it is described
Back water pump (412) is arranged in parallel.
4. nuclear power station water pressure test loop heating system according to claim 3, which is characterized in that the water inlet pipe
(311) part for being located at the charging pump (312) and heater (1) is equipped with for the moisturizing to the water inlet pipe (311) moisturizing
Interface (318) and the small pump (319) being connect with the moisturizing interface (318).
5. nuclear power station water pressure test loop heating system according to claim 1, which is characterized in that the heater (1)
Including cabinet (11), to the heating device (12) of the water heating in the cabinet (11)；
In the inside middle and lower part of the cabinet (11), the heating device (12) includes heating for heating device (12) setting
Stick.
6. nuclear power station water pressure test loop heating system according to claim 5, which is characterized in that the heater (1)
It further include temperature transmitter (13) for measuring the temperature of the water in the cabinet (11) and for measuring the cabinet
(11) liquid level detection device (14) of the water level in.
7. nuclear power station water pressure test loop heating system according to claim 1, which is characterized in that the nuclear power station hydraulic pressure
Test cycle heating system further includes water tank (5) and the water delivery that is connected between the water tank (5) and the heater (1)
It manages (6), the water-supply-pipe (6) is equipped with control valve (61) and water delivery filter (62).
8. nuclear power station water pressure test loop heating system according to any one of claims 1 to 7, which is characterized in that described
Nuclear power station water pressure test loop heating system further includes for controlling the heater (1), water inlet circuit (3), going out water loop (4)
Control system (7), the nuclear power station water pressure test loop heating system further includes for monitoring the steam generator (2)
The temperature detection part of temperature, to stop heating after the steam generator (2) reaches requirement temperature.
9. a kind of circular heating method based on any one of claim 1 to the 8 nuclear power station water pressure test loop heating system,
Characterized by comprising the following steps:
S1, the heater (1) heat water；
The water that S2, the heater (1) heat is transported in steam generator (2) through the water inlet circuit (3), to the steam
Generator (2) heating；
Water in S3, the steam generator (2) is discharged to the heater (1), return step S1 through water loop (4) out
Circulation step S1 to S3.
10. nuclear power station water pressure test circular heating method according to claim 9, which is characterized in that the water inlet branch
(31) it is equipped with the moisturizing interface for moisturizing, the circular heating method is further comprising the steps of:
After the water temperature in the loop heating system reaches target temperature, the moisturizing interface, Xiang Suoshu steam generation are opened
Device (2) interior moisturizing, reduces the water temperature in the loop heating system to lower limit temperature, and continue cycling through step S1 to S3, until institute
It states after steam generator (2) reaches requirement temperature, the heater (1) stops heating.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811565207.8A CN109799142B (en) | 2018-12-20 | 2018-12-20 | Circulating heating system and circulating heating method for nuclear power station hydrostatic test |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811565207.8A CN109799142B (en) | 2018-12-20 | 2018-12-20 | Circulating heating system and circulating heating method for nuclear power station hydrostatic test |
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| Publication Number | Publication Date |
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| CN109799142A true CN109799142A (en) | 2019-05-24 |
| CN109799142B CN109799142B (en) | 2021-11-09 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811565207.8A Active CN109799142B (en) | 2018-12-20 | 2018-12-20 | Circulating heating system and circulating heating method for nuclear power station hydrostatic test |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110579405A (en) * | 2019-08-29 | 2019-12-17 | 中广核核电运营有限公司 | Auxiliary water supply system of nuclear power station and heating method thereof |
| CN112417780A (en) * | 2020-11-19 | 2021-02-26 | 上海交通大学 | Method and system for estimating mass flow of secondary loop recycled water of steam generator |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102194535A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Pre-service hydrostatic test integrated system on secondary side of steam generator |
| CN102192819A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Quick heating process for pre-service hydrostatic test of secondary side of steam generator |
| CN102194534A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | High-precision pressing and depressing process for pre-service hydraulic pressure test of steam generator secondary side |
| CN203338776U (en) * | 2013-07-30 | 2013-12-11 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
| CN205483613U (en) * | 2016-01-23 | 2016-08-17 | 中国能源建设集团东北电力第一工程有限公司 | Large -scale power plant boiler hydrostatic test system |
| CN207263396U (en) * | 2017-09-06 | 2018-04-20 | 中广核核电运营有限公司 | Evaporator secondary side water test unit |
-
2018
- 2018-12-20 CN CN201811565207.8A patent/CN109799142B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102194535A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Pre-service hydrostatic test integrated system on secondary side of steam generator |
| CN102192819A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Quick heating process for pre-service hydrostatic test of secondary side of steam generator |
| CN102194534A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | High-precision pressing and depressing process for pre-service hydraulic pressure test of steam generator secondary side |
| CN203338776U (en) * | 2013-07-30 | 2013-12-11 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
| CN205483613U (en) * | 2016-01-23 | 2016-08-17 | 中国能源建设集团东北电力第一工程有限公司 | Large -scale power plant boiler hydrostatic test system |
| CN207263396U (en) * | 2017-09-06 | 2018-04-20 | 中广核核电运营有限公司 | Evaporator secondary side water test unit |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110579405A (en) * | 2019-08-29 | 2019-12-17 | 中广核核电运营有限公司 | Auxiliary water supply system of nuclear power station and heating method thereof |
| CN112417780A (en) * | 2020-11-19 | 2021-02-26 | 上海交通大学 | Method and system for estimating mass flow of secondary loop recycled water of steam generator |
| CN112417780B (en) * | 2020-11-19 | 2023-03-24 | 上海交通大学 | Method and system for estimating mass flow of secondary loop recycled water of steam generator |
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|---|---|
| CN109799142B (en) | 2021-11-09 |
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