CN105469846A - Auxiliary water supply system for nuclear power station steam generator - Google Patents

Auxiliary water supply system for nuclear power station steam generator Download PDF

Info

Publication number
CN105469846A
CN105469846A CN201510802269.6A CN201510802269A CN105469846A CN 105469846 A CN105469846 A CN 105469846A CN 201510802269 A CN201510802269 A CN 201510802269A CN 105469846 A CN105469846 A CN 105469846A
Authority
CN
China
Prior art keywords
steam generator
nuclear power
power station
centrifugal pump
station steam
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.)
Granted
Application number
CN201510802269.6A
Other languages
Chinese (zh)
Other versions
CN105469846B (en
Inventor
徐教珅
王志明
周亮亮
范博仁
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.)
China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Engineering 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 China General Nuclear Power Corp, China Nuclear Power Engineering Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201510802269.6A priority Critical patent/CN105469846B/en
Publication of CN105469846A publication Critical patent/CN105469846A/en
Application granted granted Critical
Publication of CN105469846B publication Critical patent/CN105469846B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/08Regulation of any parameters in the plant
    • G21D3/12Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
    • G21D3/14Varying flow of coolant
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B35/00Control systems for steam boilers
    • F22B35/004Control systems for steam generators of nuclear power plants
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention discloses an auxiliary water supply system for a nuclear power station steam generator. The auxiliary water supply system comprises a water storage tank and a centrifugal pump which are connected through multiple pipelines to form a circulation loop, a pipeline at an upstream inlet of the centrifugal pump is provided with a siphon connected with a medicine barrel, and a pipeline at a downstream outlet of the centrifugal pump is provided with a purifying device. According to the auxiliary water supply system, the inlet of the centrifugal pump is provided with the siphon connected with the medicine barrel, through siphoning before pumping, the medicine can be filled into the pipeline, the water storage tank is cleaned by utilizing power cycle of the centrifugal pump, online medicine filling is realized, risk operation such as hoisting and high altitude dosing can be avoided, and advantages of safety, convenience and rapidness are realized. The downstream outlet of the centrifugal pump is provided with the purifying device equipped with a detachable and washable filter core, and purifying demands of the water storage tank can be satisfied.

Description

Nuclear power station steam generator auxiliary feedwater system
Technical field
The invention belongs to nuclear power station debugging field, more particularly, the present invention relates to a kind of nuclear power station steam generator auxiliary feedwater system being provided with chemicals dosing plant.
Background technology
Steam generator auxiliary feedwater system system (ASG), as the engineered safety system in pressurized water reactor type, substitutes normal feedwater and provides feedwater for steam generator (SG), cooling primary Ioops when accident.Usually, every platform unit is equipped with an ASG reserve tank, auxiliary feed water pump subsystem and relevant pipeline, valve.Auxiliary feed water pump subsystem, from ASG water tank intake, is replenished in SG.When unit normally runs, store desalination/deoxygenation alkaline water in ASG reserve tank, capacity is about 1200 cubic metres.
At installation phase, installation personnel completes the sandblasting of ASG reserve tank inwall, polish, smear the operations such as water-soluble wax maintenance after, ASG reserve tank is transferred debugging.In order to ensure that ASG reserve tank is available within the phase in nuclear power station full longevity, need to do more maintenance work in the debug phase, comprising: flushing, purifying water-storage tank inner storing water, add chemicals (being mainly ammoniacal liquor and hydrazine) passivation, add the work such as chemicals adjustment water quality wet preservation.
Index Acceptability limit
Chloride <0.15mg/kg
Fluoride <0.15mg/kg
25 DEG C of cation electrodeposition conductances <1.00μs/cm
Suspension <0.1mg/kg
25 DEG C of pH value 8.8-9.8
Transparency Without muddy and sediment
Silicon ion <0.02mg/kg
ASG reserve tank in full water passivation more than 168 hours when Table A SG reserve tank water quality requirement on meeting, to form fine and close oxide film at ASG reserve tank inwall, need ensure the availability of ASG reserve tank within the nuclear power station whole phase in longevity.Except passivation maintenance, the debug phase also needs Multiple through then out to add chemicals to carry out water quality regulation, purification to ASG reserve tank.
ASG reserve tank volume is comparatively large, purifies, dosing workload is large, difficulty is high.Prior art purification ASG reserve tank, by repeatedly water-filling, draining, utilizes gravity flush ASG reserve tank.Use hanging wheel chemicals to be winched to ASG reserve tank top dosing mouth when adding chemicals, manually pour in reserve tank.By repeatedly filling draining gravity flush ASG reserve tank, often perform and once fill draining and need 1200 cubic meter of water, due to by means of only gravity flush, DeGrain, rule of thumb need to carry out 5-6 time, not only waste a large amount of demineralized water, and it is consuming time comparatively of a specified duration to fill row at every turn, completes and fill draining for 5-6 time and about need 7-9 days.
Need when adding chemicals to use hanging wheel lifting medicine, with 1200 cubic metres of water yield cheek, each dosing needs hydrazine about 25 barrels (7% concentration every barrel 20kg), the ammoniacal liquor 35 barrels (4% concentration, every barrel of 25kg) of lifting, slinging work amount is large, and dosing mouth is positioned at ASG reserve tank top simultaneously, narrow space, ventilate not smooth, use when manually pouring medicine into, pungency chemicals volatilizees in a large number, infringement staff, and has larger personnel and to fall industrial risk.
In view of this, necessaryly a kind of nuclear power station steam generator auxiliary feedwater system that safely, conveniently can complete dosing is provided.
Summary of the invention
The object of the invention is to: a kind of nuclear power station steam generator auxiliary feedwater system that safely, conveniently can complete dosing is provided.
In order to realize foregoing invention object, the invention provides a kind of nuclear power station steam generator auxiliary feedwater system, it comprises the reserve tank and the centrifugal pump that are connected into closed circuit by several pipelines, wherein, centrifugal pump upstream is provided with medicine bucket, and medicine bucket is connected on the pipeline at centrifugal pump upstream entrance place by U trap.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and the pipeline at described centrifugal pump lower exit place is provided with purification plant.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and described purification plant is the washable filter core of two row be arranged in parallel.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and the pipeline at described centrifugal pump lower exit place is provided with the differential pressure gauge in parallel with purification plant.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and described differential pressure gauge is dial type differential pressure gauge, and its range ability is 0-100kpa.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and the pipeline of washable filter core both sides is all provided with isolation valve, changes washable filter core when the pressure reduction of differential pressure gauge is greater than 20kpa.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and described U trap is provided with isolation valve.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and described pipeline is carbon steel pipe wall metallic pipe road.
One as nuclear power station steam generator auxiliary feedwater system of the present invention is improved, and described U trap is metal hose.
Relative to prior art, nuclear power station steam generator auxiliary feedwater system of the present invention has the following advantages:
1) U trap of centrifugal pump porch welding is connected in medicine bucket, by rise pump time pump before siphon medicine is added in pipeline, centrifugal pump power cycle is utilized to rinse purifying water-storage tank, realize online dosing, avoid lifting, the contour risk operations of eminence dosing, there is safety, the advantage such as easily and fast.
2) centrifugal pump lower exit pipeline place is provided with the purification plant being provided with washable filter core, meet the purification needs of reserve tank, and the aperture of filter screen of washable filter core can be changed, the initial stage uses large aperture filter screen, later stage is replaced by small-bore filter screen, meets different debug phase purification demand.
3) use equipment less, relatively cost-saving.
Accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, nuclear power station steam generator auxiliary feedwater system of the present invention is described in detail, wherein:
Fig. 1 is the structural representation of nuclear power station steam generator auxiliary feedwater system of the present invention.
Embodiment
In order to make goal of the invention of the present invention, technical scheme and technique effect thereof more clear, below in conjunction with the drawings and specific embodiments, the present invention is described in more detail.Should be understood that, the embodiment described in this instructions is only used to explain the present invention, is not intended to limit the present invention.
Refer to shown in Fig. 1, nuclear power station steam generator auxiliary feedwater system of the present invention comprises: the reserve tank 10 and the centrifugal pump 20 that are connected into closed circuit by several pipelines, wherein, the pipeline at centrifugal pump 20 upstream entrance place is provided with the U trap 30 that can be connected to medicine bucket (not shown), and the pipeline at centrifugal pump 20 lower exit place is provided with purification plant 40.
Centrifugal pump 20 for providing power for the circulation of nuclear power station steam generator auxiliary feedwater system, purification, simultaneously also for the medicine in U trap 30 adds pipeline and squeeze in reserve tank 10 and provide power.In the shown embodiment, the supply voltage of centrifugal pump 20 is 380v, adopts ventilated machine, and outlet lift is not less than 30m, and rated flow is not less than 30t/h.
U trap 30 uses metal hose, and its diameter is 15mm, U trap 30 is provided with isolation valve (T3).Before dosing is initial, closes the isolation valve on U trap 30, manually fill demineralized water from U trap 30 porch, get rid of gas in U trap 30.After starting centrifugal pump 20, U trap 30 is inserted in medicine bucket from medicine bung, and use the space between clean rag covering U trap 30 and medicine bung, volatilize to prevent pungency medicine.Manually slowly open the isolation valve before U trap 30, can be observed medicine and enter in system pipeline.After one barrel of medicine adds, repeat above-mentioned action and get final product continuous dosing.
Purification plant 40 one end connects centrifugal pump 20 lower exit place by pipeline, and the other end connects reserve tank 10 by pipeline.In the shown embodiment, purification plant 40 adopts the washable filter core of two row parallel connections, and often arranges washable filter core two ends and be all provided with stop valve (T14-T17).After circularly purifying a period of time, observe washable filter core two ends differential pressure indicator 50 registration when rising to 20kpa, centrifugal pump 20 of can stopping transport, after carrying out isolation, the lower washable filter core of dismounting cleans.Consider that water quality condition is poor at the circularly purifying initial stage, use 200 μm of washable filter cores in aperture; After water quality condition improves, use 50 μm of washable filter cores in aperture.
The differential pressure gauge 50 in parallel with purification plant 40 is provided with, for reading the pressure reduction at purification plant 40 two ends between the pipeline at purification plant 40 two ends.In the shown embodiment, differential pressure gauge 50 is dial type differential pressure gauge, and the range ability of differential pressure gauge 50 is 0-100kpa.(be greater than 20kpa) when differential pressure is higher, need idle (off-stream) unit to carry out filter core and unpick and wash work.
In nuclear power station steam generator auxiliary feedwater system of the present invention, all pipelines all use carbon steel pipe wall metallic pipe road, and for each device in connected system, pipe joint place all uses arc welding to connect.
Shown in Fig. 1, the operational process of nuclear power station steam generator auxiliary feedwater system of the present invention is as follows:
After each device is connected by pipeline, carry out water-filling exhaust to system, after measurement electrical machine insulation is qualified, start centrifugal pump 20, the size of observing washable filter core pressure reduction registration meets the requirements.
After bath exhaust is carried out to U trap 30, its entrance is inserted in medicine bucket, slowly open the isolation valve before U trap 30, start to carry out dosing.
After purification dosing work completes, stoppage in transit centrifugal pump 20, disconnects centrifugal pump 20 power supply, closes the connection valve of the isolation valve before U trap 30 and ASG reserve tank 10, emptying U trap 30.
Relative to prior art, nuclear power station steam generator auxiliary feedwater system of the present invention has the following advantages:
1) U trap 30 of centrifugal pump 20 porch is connected in medicine bucket, by rise pump time pump before siphon medicine is added in pipeline, centrifugal pump 10 power cycle is utilized to rinse purifying water-storage tank 10, realize online dosing, avoid lifting, the contour risk operations of eminence dosing, there is safety, the advantage such as easily and fast.
2) at centrifugal pump 20 lower exit pipeline place, washable filter core 40 is installed, meet the purification needs of reserve tank 10, and the aperture of filter screen of washable filter core 40 can be changed, the initial stage uses large aperture filter screen, later stage is replaced by small-bore filter screen, meets different debug phase purification demand.
3) use equipment less, relatively cost-saving.
According to above-mentioned principle, the present invention can also carry out suitable change and amendment to above-mentioned embodiment.Therefore, the present invention is not limited to embodiment disclosed and described above, also should fall in the protection domain of claim of the present invention modifications and changes more of the present invention.In addition, although employ some specific terms in this instructions, these terms just for convenience of description, do not form any restriction to the present invention.

Claims (9)

1. a nuclear power station steam generator auxiliary feedwater system, comprise the reserve tank and the centrifugal pump that are connected into closed circuit by several pipelines, it is characterized in that: described centrifugal pump upstream is provided with medicine bucket, and medicine bucket is connected on the pipeline at centrifugal pump upstream entrance place by U trap.
2. nuclear power station steam generator auxiliary feedwater system according to claim 1, is characterized in that: the pipeline at described centrifugal pump lower exit place is provided with purification plant.
3. nuclear power station steam generator auxiliary feedwater system according to claim 2, is characterized in that: described purification plant is the washable filter core of two row be arranged in parallel.
4. the nuclear power station steam generator auxiliary feedwater system according to Claims 2 or 3, is characterized in that: the pipeline at described centrifugal pump lower exit place is provided with the differential pressure gauge in parallel with purification plant.
5. nuclear power station steam generator auxiliary feedwater system according to claim 4, is characterized in that: described differential pressure gauge is dial type differential pressure gauge, and its range ability is 0-100kpa.
6. nuclear power station steam generator auxiliary feedwater system according to claim 5, is characterized in that: the pipeline of washable filter core both sides is all provided with isolation valve, changes washable filter core when the pressure reduction of differential pressure gauge is greater than 20kpa.
7. nuclear power station steam generator auxiliary feedwater system according to claim 1, is characterized in that: described U trap is provided with isolation valve.
8. nuclear power station steam generator auxiliary feedwater system according to claim 1, is characterized in that: described pipeline is carbon steel pipe wall metallic pipe road.
9. nuclear power station steam generator auxiliary feedwater system according to claim 1, is characterized in that: described U trap is metal hose.
CN201510802269.6A 2015-11-18 2015-11-18 Nuclear power station steam generator auxiliary feedwater system Active CN105469846B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201510802269.6A CN105469846B (en) 2015-11-18 2015-11-18 Nuclear power station steam generator auxiliary feedwater system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201510802269.6A CN105469846B (en) 2015-11-18 2015-11-18 Nuclear power station steam generator auxiliary feedwater system

Publications (2)

Publication Number Publication Date
CN105469846A true CN105469846A (en) 2016-04-06
CN105469846B CN105469846B (en) 2018-07-20

Family

ID=55607461

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201510802269.6A Active CN105469846B (en) 2015-11-18 2015-11-18 Nuclear power station steam generator auxiliary feedwater system

Country Status (1)

Country Link
CN (1) CN105469846B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108511090A (en) * 2018-03-08 2018-09-07 中国核电工程有限公司 A kind of cooling water tank component of nuclear power plant's secondary side passive cooling system
CN110486709A (en) * 2019-08-15 2019-11-22 岭澳核电有限公司 A kind of nuclear power station steam generator drainage

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN1085005A (en) * 1992-09-29 1994-04-06 清华大学 Siphon tube type gravity boron implantation system for reactor
CN1437751A (en) * 2000-12-14 2003-08-20 埃斯科姆公司 Cooling system
CN201232666Y (en) * 2008-08-04 2009-05-06 天津市津风特种风机技术开发有限公司 Blower fan with filter box
US20100232560A1 (en) * 2007-12-27 2010-09-16 Mitsubishi Heavy Industries, Ltd. Ph adjusting system and ph adjusting method
CN202113829U (en) * 2011-05-26 2012-01-18 苏州森泰动力环保工程有限公司 Air purifying device with automatic fluid-phase chemical feeding system
CN204010702U (en) * 2014-06-03 2014-12-10 中国核电工程有限公司 A kind of steam generator emergency feedwater supply system
CN104925922A (en) * 2015-05-13 2015-09-23 韩炳申 Rapid sewage purifier

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN1085005A (en) * 1992-09-29 1994-04-06 清华大学 Siphon tube type gravity boron implantation system for reactor
CN1437751A (en) * 2000-12-14 2003-08-20 埃斯科姆公司 Cooling system
US20100232560A1 (en) * 2007-12-27 2010-09-16 Mitsubishi Heavy Industries, Ltd. Ph adjusting system and ph adjusting method
CN201232666Y (en) * 2008-08-04 2009-05-06 天津市津风特种风机技术开发有限公司 Blower fan with filter box
CN202113829U (en) * 2011-05-26 2012-01-18 苏州森泰动力环保工程有限公司 Air purifying device with automatic fluid-phase chemical feeding system
CN204010702U (en) * 2014-06-03 2014-12-10 中国核电工程有限公司 A kind of steam generator emergency feedwater supply system
CN104925922A (en) * 2015-05-13 2015-09-23 韩炳申 Rapid sewage purifier

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
刘锦华等: "《岭澳核电工程实践与创新调试启动卷(I)》", 31 July 2003, 原子能出版社 *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108511090A (en) * 2018-03-08 2018-09-07 中国核电工程有限公司 A kind of cooling water tank component of nuclear power plant's secondary side passive cooling system
CN110486709A (en) * 2019-08-15 2019-11-22 岭澳核电有限公司 A kind of nuclear power station steam generator drainage

Also Published As

Publication number Publication date
CN105469846B (en) 2018-07-20

Similar Documents

Publication Publication Date Title
CN109323237B (en) Method for using nuclear grade polyacrylic acid dispersant for wet maintenance of steam generator of nuclear power plant
CN105469846A (en) Auxiliary water supply system for nuclear power station steam generator
CN204261450U (en) The brush spotter of a kind of Novel hand-power
CN205264348U (en) Radioactive waste liquid resin receiving arrangement
CN102188927A (en) Automatic proportioning system of emulsified liquid and hydraulic feed system
CN204752245U (en) Exhaust type is sour, alkali batch meter
CN110882975A (en) Method for cleaning pipeline before production stop, inspection and maintenance of high-sulfur-content station
CN103279092A (en) Centralized control system for long-distance pipeline coal transporting terminal station equipment and control method of centralized control system
CN103939747B (en) A kind of Slurry Pipeline Transportation system and method for low corrosion
CN204608874U (en) A kind of huge tanks descaling sterilization device
US9687891B2 (en) Intake pipe cleaning system and method
CN203275982U (en) Centralized control system of long-distance pipeline coal-transporting terminal station device
CN202371696U (en) On-line cleaning steam boiler device
CN206486378U (en) A kind of diesel locomotive cools down water preparation apparatus
CN207845311U (en) A kind of cutting wastewater processing system
CN204380379U (en) A kind of nitric acid exhaust system
CN214211627U (en) Handheld decontamination device for nuclear power station
CN208074594U (en) A kind of blowdown collection conveying device
CN201625463U (en) Vertical expanding-type dirt separator
CN214780921U (en) High concentration waste water submergence formula ultrafiltration system
CN203469821U (en) Flushing-washing device of antiosmosis system
CN206970331U (en) A kind of desulfurization wastewater treatment system
CN202349989U (en) Shut-down protection octadecylamine dosing device
CN203648207U (en) Oil filtering tank
CN213356938U (en) Storage tank system is unloaded to acid-base dangerous chemicals

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant