CN102477978A - Nuclear grade pump identification test loop system - Google Patents
Nuclear grade pump identification test loop system Download PDFInfo
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- CN102477978A CN102477978A CN2010105664231A CN201010566423A CN102477978A CN 102477978 A CN102477978 A CN 102477978A CN 2010105664231 A CN2010105664231 A CN 2010105664231A CN 201010566423 A CN201010566423 A CN 201010566423A CN 102477978 A CN102477978 A CN 102477978A
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- 238000013095 identification testing Methods 0.000 title abstract 2
- 238000012360 testing method Methods 0.000 claims abstract description 82
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 74
- 238000003860 storage Methods 0.000 claims abstract description 23
- 230000035939 shock Effects 0.000 claims abstract description 18
- 238000005485 electric heating Methods 0.000 claims abstract description 12
- 238000010438 heat treatment Methods 0.000 claims abstract description 7
- 238000011056 performance test Methods 0.000 claims abstract description 7
- 238000011156 evaluation Methods 0.000 claims description 13
- 239000000498 cooling water Substances 0.000 claims description 10
- 235000014121 butter Nutrition 0.000 claims description 9
- 238000012544 monitoring process Methods 0.000 claims description 5
- 239000012535 impurity Substances 0.000 abstract description 8
- 238000000034 method Methods 0.000 abstract description 4
- 230000000087 stabilizing effect Effects 0.000 abstract 2
- 230000004807 localization Effects 0.000 abstract 1
- 238000001816 cooling Methods 0.000 description 12
- 230000008878 coupling Effects 0.000 description 10
- 238000010168 coupling process Methods 0.000 description 10
- 238000005859 coupling reaction Methods 0.000 description 10
- 230000003020 moisturizing effect Effects 0.000 description 8
- 238000013461 design Methods 0.000 description 7
- 238000007789 sealing Methods 0.000 description 5
- 239000002826 coolant Substances 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 238000010304 firing Methods 0.000 description 3
- 239000002184 metal Substances 0.000 description 3
- 230000001105 regulatory effect Effects 0.000 description 3
- 238000004804 winding Methods 0.000 description 3
- 229910000975 Carbon steel Inorganic materials 0.000 description 2
- 229920002943 EPDM rubber Polymers 0.000 description 2
- 239000010962 carbon steel Substances 0.000 description 2
- 230000006835 compression Effects 0.000 description 2
- 238000007906 compression Methods 0.000 description 2
- 238000013481 data capture Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000002474 experimental method Methods 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000008399 tap water Substances 0.000 description 2
- 235000020679 tap water Nutrition 0.000 description 2
- 238000005299 abrasion Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000008367 deionised water Substances 0.000 description 1
- 229910021641 deionized water Inorganic materials 0.000 description 1
- 239000004744 fabric Substances 0.000 description 1
- 230000008676 import Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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Abstract
A nuclear grade pump identification test loop system is composed of a main test loop section and a water replenishing system. The main test loop section comprises a test pump, a sleeve type cooler, an electric heating device outside a pipeline, an electric heating element water storage tank, a pressure stabilizing tank, a Venturi flowmeter, two electric ball valves QV2, a QV3, an electric adjusting ball valve BV1 and a three-way pneumatic ball valve TV 1. The water replenishing system is formed by connecting a water replenishing pipe with a test pump, a circulating pump inlet and the bottom of a pressure stabilizing tank through three branches. The main test loop and the heating circulation loop are matched together to complete a test pump performance test, a thermal shock test, an impurity test and a durability test. The method is good for realizing the localization of the nuclear pump.
Description
Technical field: the present invention relates to domestic a kind of nuclear level pump evaluation test circuit system.
Background technique: in the R&D process of nuclear level pump, evaluation test is in the R&D process and important link.Under normal and emergency conditions, accomplish the ability of design function in order to verify pump assembly; The experimental prototype unit of pump need carry out a series of test under rigors; To guarantee that product satisfies system requirements; Therefore the design of examining pump evaluation test system is very crucial, is that the production domesticization of nuclear level pump product has important practical significance.
Nuclear level pump evaluation test mainly comprises endurance test, performance test, thermal shock test, dirl butter etc.
1. endurance test requires the target flow point continuous running of model machine unit under the high temperature media situation up to a hundred hours, comprises the start stop operation of stipulated number.One adopts closed cycle loop, the design demand account temperature requirement of pipeline test stand.
2. performance test all has requirement to loop temperature, pressure; Consider heating, temperature control device for the design demand of performance test stand; The general Electric heating that adopts heats loop medium, adopts the heat exchanger of enough exchange capability of heat that temperature is regulated simultaneously.
3. thermal shock test requires the instantaneous variation of pressure, temperature, generally adopts the quick conversion regime in loop to carry out.
4. dirl butter is mainly investigated model machine at " dirty " medium, promptly contains conveyance capacity and abrasion condition under the ambient condition of regulation ratio impurity.
Summary of the invention: the object of the invention will provide a kind of nuclear level pump evaluation test circuit system exactly, and it can carry out above test by the designing requirement of nuclear level pump.The objective of the invention is to realize like this; A kind of nuclear level pump evaluation test circuit system; Form by master trip loop sections, water charging system; It is characterized in that: master trip loop and heat cycles loop cooperate jointly, accomplish test pump performance test, thermal shock test, dirl butter, endurance test.
Described sealed member is the whole integrated mechanical sealing that adopts single end face, state type, balance row, and the required O RunddichtringO that uses of each component is ethylene propylene diene rubber, on flange facing, adopts the metal winding type pad with stiffening ring.
Described carriage member is made up of support, pump seat, adopts the intermediate support mode, and support adopts carbon steel material, is provided with stiffening rib in yielding part.
Described coupling parts are made up of pump end coupling, motor side coupling, have adopted the heat expansion interference fit between electric machine main shaft and the coupling axle sleeve.
Described cooling system is that to be provided with cooling water jecket in the mechanical seal periphery be circulation cooling circuit, behind pump cover, has designed the cooling loop structure, in the bearing support outer installment recirculated cooling water runner of ring channel structures, and be provided with coolant jacket above that; On mechanical seal cooling circuit, cools down pipeline, designed data capture, monitoring sensor, monitored, and supervisory signal has been passed to the centralized control end for loop medium temperature, flow and pressure parameter.
The present invention takes into full account shockproof requirements in overall construction design, through improving integral rigidity, reducing overall weight.Final through Seismic Analysis, shock test, experiments of sealing performance, monitoring temperature can both meet design requirement on overall structure antidetonation, sealability, temperature, material property.
Description of drawings: Fig. 1 is a structural representation of the present invention;
1. support, 2. radial thrust bearing group, 3. bearing support, 4. coolant jacket, 5. mechanical seal, 6. pump shaft, 7. pump cover, 8. outlet(discharge) flange, the 9. pump housing, 10. stator, 11. impellers, 12. suction flanges, 13. cooling water jeckets, 14. roller bearings, 15. cooling chambers.
Embodiment: the present invention is described further below in conjunction with accompanying drawing;
A kind of compressed water reactor nuclear power unit is used residual heat removal pump; Form by stator component, rotor part, Sealing, carriage member, coupling parts, cooling system; It is characterized in that: adopt the horizontal centrifugal pump of one step single sucking, the overall structure that the pump housing has adopted axial suction, radially discharged.
Described stator component is made up of the pump housing 9, pump cover 7, stator 10, outlet(discharge) flange 8,12 of suction flanges.
Described rotor part is made up of 14 of radial thrust bearing group 2, the roller bearings of impeller 11, pump shaft 6 and support pump shaft.
Described sealed member is the whole integrated mechanical sealing that adopts single end face, state type, balance row, and the required O RunddichtringO that uses of each component is ethylene propylene diene rubber, on flange facing, adopts the metal winding type pad with stiffening ring.
Described carriage member is made up of support 1, pump seat, adopts the intermediate support mode, and support adopts carbon steel material, is provided with stiffening rib in yielding part.
Described coupling parts are made up of pump end coupling, motor side coupling, have adopted the heat expansion interference fit between electric machine main shaft and the coupling axle sleeve.
Described cooling system; Be to be provided with cooling water jecket 13 to be circulation cooling circuit in mechanical seal 5 peripheries; Behind pump cover 7, designed the cooling loop structure, in bearing support 3 outer installment the recirculated cooling water runner of ring channel structures, and be provided with coolant jacket 4 above that; On mechanical seal 5 cooling circuits, cools down pipeline, designed data capture, monitoring sensor, monitored, and supervisory signal has been passed to the centralized control end for loop medium temperature, flow and pressure parameter.
During practical implementation; The integral arrangement that the pump housing adopts axially and sucks, radially discharges; And the inlet/outlet flange is directly installed on the pump housing imports and exports the surface, reduced processing, welding and the installation procedure of pump housing pressure part, increased this parts bearing capacity simultaneously; And on flange facing, adopt metal winding type pad with stiffening ring, guaranteed the sealing of importing and exporting.
The pump housing, motor adopt the design of base separated type; The transportation and the on-the-spot Installation and Debugging of pump assembly have been made things convenient for; Between the pump housing and motor, adopt the flexible membrane coupling; Allow certain centering distortion inaccuracy, at motor master primary stainless steel pipeline, parallel connection ￠ 60X4 branch road adds section as impurity at motorized adjustment ball valve two ends.The loop adopts electric reciprocating pump to carry out moisturizing, and can be to being forced into 2MPa behind the full water of loop.
Water-adding pipe divides three branch roads to link to each other with test pump, pump inlet place and surge tank bottom, respectively by stop valve JV5, JV3 and JV6 control.
Water storage tank is storage, heat medium effect.Water storage tank is connected through two interfaces with major loop, a high-end low side, and high termination thermal shock major loop comes water, hot water or cooling water outlet when low side is thermal shock test; Arrange each one on level meter, outlet valve and safety valve on the water storage tank; The intermediate arrangement electrical heating elements to jar in water heat, go back cloth temperature and pressure in two temperature measuring equipments and the pressure gauge monitoring water storage tank in a twinkle on jar.
Surge tank plays the effect of stablizing the master trip circuit pressure, and surge tank is taken over through the bottom and is connected to the test pump inlet duct.In addition, the surge tank bottom is taken over and is connected water-adding pipe, can independently carry out moisturizing and pressurization to surge tank.
Two coolers are set, and primary cooler is parallelly connected with the loop, outside the removal of impurity test, all can drop into and be used for the stable loop water temperature.Arranged double-pipe cooler on the main pipe, be mainly used in the dirl butter control, also can be used under other operating condition of test cooling simultaneously the loop to water temperature.
The loop test function: master trip loop and heat cycles loop cooperate jointly, accomplish all contents of the test of test pump.Water charging system can carry out moisturizing for respectively major loop section and heat cycles loop sections, also can carry out moisturizing to surge tank separately; But the heat-exchange system coolant temperature is realized the temperature control to device; Stable-pressure device can be realized the pressure adjusting in loop, and water tank storage test water adopts tap water during dirl butter, and thermal shock test adopts deionized water; Exhaust when vent systems is used for to loop moisturizing and normal temperature operation.
Performance test: carry out residual heat removal pump under various operating modes during the hydraulic characteristic parameter determination test; Only need on the master trip loop, carry out; The heat cycles loop that cut-out links to each other with major loop; Promptly close electric ball valve QV1, QV4, three-way valve is redirect to the test pump inlet, determine whether to drop into cooler according to loop water temperature in the test.In addition, when carrying out cavitation experiment, be connected with vacuum pump, reduce the cavitation amount that the test pump inlet pressure reaches test requirements document through the adapter of surge tank top.
Thermal shock test: before carrying out the thermal shock test first time, need promptly to cut off electric ball valve QV2 and to open electric ball valve QV3 soon except that test pump and the loop water heating of importing and exporting the section earlier; Three-way valve turns to the water storage tank inlet, starts heat cycles pump and two cover electric heating systems, opens the valve on the heat cycles loop; After the water temperature in major loop and the water storage tank reaches 200 ℃, stop heating circuit operation termination of pumping, cut off electric heating, adding ice cube in the water supply tank; When water temperature is reduced to below 20 ℃, start the moisturizing compression pump, open water-feeding valve JV5 moisturizing in test pump; And exhaust of top, loop or water, make to be full of fully in the test pump to be lower than 20 ℃ water, close outlet valve; Continuation is closed water-feeding valve JV5 after being added to 3MPa through compression pump.Thermal shock test begins, and breaks off the heat cycles loop and closes QV4, opens test pump inlet valve QV3, and the cold water in the test pump is entered in the water storage tank, and the hot water in the water storage tank enters into test pump, reaches the thermal shock test purpose in the 10S.When three-way valve front end cold water flows through, three-way valve preceding pipeline temperature is monitored, and three-way valve TV1 is switched in the test pump inlet fast; And close water storage tank outer pipe valve QV1 and form and to be independent of soft circulation circuit outside the water storage tank; This loop need be moved four hours, and loop water temperature is through double-pipe cooler and outer electric heating system of pipe and water temperature interlocked control, when water temperature is higher than 200 ℃; Stop electric heating, and maximum flow drops into double-pipe cooler; When water temperature is lower than 180 ℃, turn or close cooling water down, start the outer electric heating of pipe, loop water temperature is stabilized between 180 ℃-200 ℃.After accomplishing thermal cycle in four hours, two coolers are dropped into together, the master trip loop is lowered the temperature, when loop water temperature reaches 60 ℃, according to the flow of loop water temperature control cooler, make water temperature stability again
60 ℃ of operations four hours.Before the thermal shock test, all circuit systems are in the normal temperature state for the second time.Break off the heat cycles loop, promptly cut off QV1, QV4, three-way valve redirect in the test pump inlet, the outer electric heating system of firing test pump and main pipe; In three hours, this loop water temperature is risen to 180 ℃, stop the test pump operation then, close QV2 and QV3, open QV4; Three-way valve redirect to the water storage tank inlet, starts recycle pump, with the cold water mix of hot water in the main pipe and water storage tank; Drop into cooler as required, during for fear of cold shock, the pipeline section material is to the lifting of loop water temperature; Fully mix the back water temperature and be not higher than 60 ℃, stop recycle pump, close QV4.Open valve QV2, the firing test pump is opened valve QV3 fast, and the hot water in the test pump is entered in the water storage tank, and the cooling water in the water storage tank enters into test pump, reaches the cold shock test objective in the 10S.After three-way valve front end flow of hot water; Switch to fast in the test pump inlet, form and be independent of cooling circuit outside the water storage tank＜80 ℃, this loop need be moved four hours; Loop temperature is stabilized under 80 ℃ loop water temperature through double pipe heat exchanger and primary cooler control.
Dirl butter: dirl butter adopt tap water to major loop moisturizing open JV4; Test need be carried out in two stages; At first cut off the heat cycles loop, promptly close QV1 and QV4, and the valve QV5 and the QV6 that connect primary cooler; Three-way valve TV1 steering test pump intake, the outer electric heating system of firing test pump and pipeline is heated to 180 ℃ with major loop water.After loop water temperature reaches 180 ℃, open impurity and add inlet, ready impurity is joined in the pipe; And fills with water rear enclosed; Slowly open stop valve JV12 and JV13, and change the aperture of regulating ball valve BV1, make the water of major loop flow through impurity interpolation section; Impurity is brought in the major loop gradually, reaches the purpose of dirl butter.The water temperature that relies on double-pipe cooler and the outer electric heating stable loop of pipe is more than 180 ℃.
Endurance test: waste heat is discharged 200 hours endurance test of test pump and can on the master trip loop that is independent of outside the water storage tank, be carried out; The loop flow is regulated through modulating valve BV1 and is reached the test requirements document flow, and water temperature adopts the primary cooler cooling water inflow to control.
Claims (6)
1. examine level pump evaluation test circuit system for one kind; Form by master trip loop sections, water charging system; It is characterized in that: master trip loop and heat cycles loop cooperate jointly, accomplish test pump performance test, thermal shock test, dirl butter, endurance test.
2. a kind of nuclear level pump evaluation test circuit system according to claim 1; It is characterized in that: described master trip loop sections; Be that a motorized adjustment ball valve BV1 (19) and a threeway pneumatic ball valve TV1 (18) form by test pump (2), double-pipe cooler (6), the outer electric heating (3) of pipeline, charged heating element water storage tank (11), surge tank (26), a Venturi meter (4), two electric ball valve QV2 (23), QV3 (5).
3. a kind of nuclear level pump evaluation test circuit system according to claim 1; It is characterized in that: described water storage tank (11) is connected through two interfaces with major loop; A high-end low side, high termination thermal shock major loop comes water, hot water or cooling water outlet when low side is thermal shock test; Arrange each one on level meter, outlet valve and safety valve on the water storage tank; The intermediate arrangement electrical heating elements to jar in water heat, also arrange temperature and pressure in two temperature measuring equipments and pressure gauge monitoring water storage tank on the jar.
4. a kind of nuclear level pump evaluation test circuit system according to claim 1, it is characterized in that: described surge tank (26) is taken over through the bottom and is connected to test pump (2) inlet duct; In addition, surge tank (26) bottom is taken over and is connected water-adding pipe.
5. a kind of nuclear level pump evaluation test circuit system according to claim 1 is characterized in that: described cooler, and a primary cooler (10) is parallelly connected with major loop, and another double-pipe cooler (6) is arranged on the main pipe.
6. a kind of nuclear level pump evaluation test circuit system according to claim 1; It is characterized in that: described water charging system; Be to divide three branch roads to link to each other, respectively by stop valve JV5 (25), JV3 (15) and JV6 (24) control with test pump (2), recycle pump (12) inlet and surge tank (26) bottom by water-adding pipe.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010105664231A CN102477978A (en) | 2010-11-25 | 2010-11-25 | Nuclear grade pump identification test loop system |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010105664231A CN102477978A (en) | 2010-11-25 | 2010-11-25 | Nuclear grade pump identification test loop system |
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| CN102477978A true CN102477978A (en) | 2012-05-30 |
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| CN2010105664231A Pending CN102477978A (en) | 2010-11-25 | 2010-11-25 | Nuclear grade pump identification test loop system |
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Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103437990A (en) * | 2013-07-17 | 2013-12-11 | 上海硕翼机电设备有限公司 | Thermal shock testing method and system for pump |
| CN104776038A (en) * | 2015-05-05 | 2015-07-15 | 上海阿波罗机械股份有限公司 | Nuclear power station main water feed pump thermal impact property testing system |
| CN104806534A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | System for testing variable rotating speed performance of main water feed pump of nuclear power station |
| CN104806533A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | System for testing thermal-state durability of main water feed pump of nuclear power station |
| CN104806532A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | Test loop of main water feed pump of nuclear power station |
| CN104806509A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | System for testing cavitation performance of main water feed pump of nuclear power station |
| CN105485042A (en) * | 2016-01-07 | 2016-04-13 | 江苏海狮泵业制造有限公司 | Thermal shock test device of normal residual heat removal pump |
| CN105976689A (en) * | 2016-05-06 | 2016-09-28 | 上海核工程研究设计院 | Multifunctional testing device used for control rod drive wire rod drop test and fuel assembly service lifetime test |
| CN107269548A (en) * | 2017-08-15 | 2017-10-20 | 上海电气凯士比核电泵阀有限公司 | One seed nucleus level pump impurity tester and its test method |
| CN107816431A (en) * | 2017-11-23 | 2018-03-20 | 山东省农业机械科学研究院 | Core two level high-pressure safe injection pump environmental simulation pilot system |
| CN111059043A (en) * | 2019-12-23 | 2020-04-24 | 王佳元 | Novel roots vacuum pump test system |
| CN111306075A (en) * | 2019-12-20 | 2020-06-19 | 哈尔滨电气动力装备有限公司 | Accidental test system for reactor coolant pump plant-wide power failure |
| CN113776753A (en) * | 2021-10-15 | 2021-12-10 | 上海电气凯士比核电泵阀有限公司 | Test loop and test method for testing mechanical seal for nuclear main pump |
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Cited By (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103437990A (en) * | 2013-07-17 | 2013-12-11 | 上海硕翼机电设备有限公司 | Thermal shock testing method and system for pump |
| CN103437990B (en) * | 2013-07-17 | 2019-03-22 | 上海硕翼机电设备有限公司 | Pump thermal shock test method and system |
| CN104806532A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | Test loop of main water feed pump of nuclear power station |
| CN104776038A (en) * | 2015-05-05 | 2015-07-15 | 上海阿波罗机械股份有限公司 | Nuclear power station main water feed pump thermal impact property testing system |
| CN104806534A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | System for testing variable rotating speed performance of main water feed pump of nuclear power station |
| CN104806509A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | System for testing cavitation performance of main water feed pump of nuclear power station |
| CN104806533A (en) * | 2015-05-05 | 2015-07-29 | 上海阿波罗机械股份有限公司 | System for testing thermal-state durability of main water feed pump of nuclear power station |
| CN104806533B (en) * | 2015-05-05 | 2016-05-04 | 上海阿波罗机械股份有限公司 | The hot endurance quality pilot system of a kind of nuclear power station main feed pump |
| CN105485042A (en) * | 2016-01-07 | 2016-04-13 | 江苏海狮泵业制造有限公司 | Thermal shock test device of normal residual heat removal pump |
| CN105485042B (en) * | 2016-01-07 | 2017-10-27 | 江苏海狮泵业制造有限公司 | A kind of normal residual heat removal pump thermal shock rig |
| CN105976689A (en) * | 2016-05-06 | 2016-09-28 | 上海核工程研究设计院 | Multifunctional testing device used for control rod drive wire rod drop test and fuel assembly service lifetime test |
| CN107269548A (en) * | 2017-08-15 | 2017-10-20 | 上海电气凯士比核电泵阀有限公司 | One seed nucleus level pump impurity tester and its test method |
| CN107816431A (en) * | 2017-11-23 | 2018-03-20 | 山东省农业机械科学研究院 | Core two level high-pressure safe injection pump environmental simulation pilot system |
| CN107816431B (en) * | 2017-11-23 | 2024-06-04 | 山东省农业机械科学研究院 | Nuclear second-level high-pressure safety injection pump environment simulation test system |
| CN111306075A (en) * | 2019-12-20 | 2020-06-19 | 哈尔滨电气动力装备有限公司 | Accidental test system for reactor coolant pump plant-wide power failure |
| CN111059043A (en) * | 2019-12-23 | 2020-04-24 | 王佳元 | Novel roots vacuum pump test system |
| CN113776753A (en) * | 2021-10-15 | 2021-12-10 | 上海电气凯士比核电泵阀有限公司 | Test loop and test method for testing mechanical seal for nuclear main pump |
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Application publication date: 20120530 |