CN85106507A - Improved model steam generator - Google Patents
Improved model steam generator Download PDFInfo
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- CN85106507A CN85106507A CN198585106507A CN85106507A CN85106507A CN 85106507 A CN85106507 A CN 85106507A CN 198585106507 A CN198585106507 A CN 198585106507A CN 85106507 A CN85106507 A CN 85106507A CN 85106507 A CN85106507 A CN 85106507A
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Abstract
One is used for simulating the improvement model steam generator of condition in the nuclear boiler, and in order to the heat exchanger tube of supervision nuclear boiler and the situation of tube sheet, this generator has a tripping device, be used in the steam that the separating evaporator secondary side flows out with water droplet.This device is made up of many bolters, each bolter has one group of semi-cylindrical deflecting plate, each is organized the adjacent relatively bolter deflecting plate of parallel deflecting plate deflection at 45 and arranges, so that one curved channel is arranged to the vapor stream at upper reaches, this generator also has a condenser device that can divide into groups, and it has improved the adjusting ratio greatly; And a feed water preheater is arranged, with the thermal-hydraulic condition of multiple spot on the model steam generator tube sheet.
Description
The present invention touches upon and is used for supervising the model steam generator of nuclear boiler heat exchanger tube corrosion.
Be used for supervising some type simulation steam generator of the corrosion failure amount that the nuclear boiler heat exchanger tube takes place, normally known in the former technology.In general, this model steam generator be by make one group of sample heat exchanger tube bear in the nuclear boiler heat exchanger tube around identical heat, pressure and electrochemical conditions come work.If these conditions are accurately simulated, then the etching extent that takes place in the model steam generator sample heat exchanger tube will accurately indicate the pipe corrosion that is existed in the nuclear boiler of supervising.This model steam generator is a kind of useful especially form of corrosion monitoring, and nuclear power station does not need to send the technician to enter the active inside of steam generator to go yet because they do not need to close down.But, only can accurately simulate under the situation of the heat, pressure and the electrochemical conditions that exist in the nuclear power station at this model steam generator, they are only useful.Anyly will produce adverse influence to the precision of model steam generator to departing from all of these conditions.
In order to understand the difficulty in building the practical model steam generator that the corrosion of an exchange heat pipe provides accurate supervision, people must understand at first how nuclear boiler normally to construct, and which type of chemistry and hydraulics can cause pipe to corrode.
Nuclear boiler is made up of three major parts, and it comprises the primary side that adds hot water of a secondary side, a tube sheet and a circulation nuclear reactor.The secondary side of steam generator comprises many U-shaped pipes and an entrance sleeve that imports feedwater flow.The entrance and exit end of U-shaped pipe is installed on the tube sheet in secondary side, and this tube sheet is separated the primary side of steam generator and secondary side on waterpower.Primary side comprises distribution plate again, and distribution plate is kept apart the inlet end and the endpiece of U-shaped pipe on waterpower.The hot water that comes from nuclear reactor stream imports the part that primary side comprises all inlet ends of U-shaped pipe.Flow of hot water is crossed inlet, upwards by tube sheet and around the U-shaped circulation that extends in the steam generator secondary side.Hot water is sent to its heat in the feedwater of flowing through steam generator secondary side by the tube wall of U-shaped pipe, thereby converts feedwater to steam.Nuclear add hot water circulation by the U-shaped pipe after, it flows through the outlet of tube sheet, U-shaped pipe, the exit portion that enters primary side is back to nuclear reactor then.The inlet end of U-shaped pipe is referred to as " hot arc ", and the endpiece of these pipes is referred to as " cold section ".
The heat exchanger tube of this nuclear boiler may suffer many multi-form corrosion failures, comprises constriction, stress corrosion cracking (SCC), intracrystalline corrosion and tubercular corrosion.Site inspection to the pipe of these steam generators has been found that this corrosion failure great majority occur in the crack district that is referred to as steam generator.This crack district comprise between heat exchanger tube and tube sheet the annular gap and in these pipes and secondary side the annular gap between the various back up pads, these back up pads are used for separating equably and locating these pipes.The corrosivity sludge is owing to the effect of gravity trends towards being collected in these cracks.In addition, waterpower circulation relatively poor in these districts trends towards making sludge to remain in these cracks, and is causing concentrated " focus " near in the pipe of sludge.The corrosive compound of heat in outside surface that causes heat exchanger tube and sludge that these " focuses " give off carries out playing on the chemical combination strong catalyst action.Though most nuclear boiler includes drainage, be used for termly sludge removal being gone out steam generator shell, the sludge in the crack district is to be not easy to wash out with the flow of pressurized that this drainage produces.Although the heat exchanger tube of this nuclear boiler is generally made with corrosion resistant Inco nickel (Inconec) stainless steel, but the combination of regional area heat and corrosivity sludge may cause that finally heat exchanger tube breaks, and the radioactive water of primary side is leaked in the secondary side of steam generator.Yet,, just do not had this deficiency if before corrosion causes tube wall generation crackle, the enhancing sleeve pipe was housed in heat exchanger tube inside.
For the corrosion failure amount that takes place in the heat exchanger tube of accurately monitoring specific nuclear boiler, improved model steam generator, its purpose is can give before any tube wall breaks these pipes to load onto sleeve pipe.Have been found that this model steam generator is the accurate especially method of the corrosion failure amount that takes place in a kind of definite kernel steam generator heat exchange tube, because the particular etch amount that the feedwater chemical property of specific steam generator and hot-working hydraulic characteristic cause is actually and can not predicts with pure theoretical model in the specific tube group.
Yet the model steam generator of this employing prior art exists some great problems.For example, some this model steam generator has no idea water is separated from their wet steams that produce, that secondary side comes out.This makes the compound of generation sludge of a great deal of overflow by the water droplet that is entrained in the steam, thereby has weakened the ability of the sludge amount that accumulates in the accurate model steam generator of this model.In order to proofread and correct this inexactness, some model steam generator adopts the helical blade that uses in the full-scale steam generator or the scaled model of separator.
This helical blade or separation vessel are a sheet metal constantly to be rotated carry out work in the steam plume that model steam generator produces, this piece sheet metal collides many water droplets of being entrained in this steam plume and their is thrown and hits on the inwall of steam generator secondary side, and they flow back down in the feed trough in the secondary side there.Though the scaled model of this helical blade type separation vessel is effectively to most of water droplets of carrying secretly in the steam of removing the generation of model steam generator secondary side, 0.25% loss percentage that loss percentage is still had far above helical blade type separation vessel in the nuclear boiler that simulated.Because aspect the water droplet of being carried secretly in the steam of removing the generation of model steam generator secondary side, the efficient of ratio scaled-down version helical blade type separation vessel is not pro rata.Therefore these model steam generators have bigger water loss and flow through their steam output pipe road.These water losses cause the compound of the generation sludge of a great deal of to be ejected the steam outlet pipe of secondary side again.This has delayed the sludge formation in the model steam generator again, and the delaying of this sludge formation has influence on accuracy of simulation in a kind of extrahazardous mode.The operator of model steam generator may obtain false impression, i.e. near the sludge of the corrosion pipe that accumulates tube sheet of the nuclear boiler of being supervised little than its actual accumulation.
Comprise also that with other weak point of the model steam generator of prior art manufacturing they can not accurately simulate the condition of heat exchanger tube and tube sheet in the steam generator zones of different.Or rather, many model steam generators that have earlier can not be simulated the internal circulating load and the thermoflux at difference place on the radial direction of the nuclear boiler tube sheet of being supervised.In addition, the model steam generators before many can not be simulated " small throughput " and " high flux " two kinds of conditions easily, and these conditions output to from its minimum steam at nuclear boiler and exist when the highest steam is exported.
Obviously, the steam separator that requires model steam generator to have can make the damage by water vector by the steam generator secondary side steam outlet pipe be reduced to the suitable degree of in esse damage by water vector in the quilt nuclear boiler of supervising, so that can accurately simulate near the sludge accumulation that exists this steam generator tube sheet.In theory, this model steam generator can also be simulated the thermal-hydraulic feature of any point on the nuclear boiler tube sheet radial direction accurately, easily.At last, this model steam generator should be able to be simulated " hot arc " and " cold section " condition on every side of heat exchanger tube in the range of adjustment of broad.
The present invention mainly includes an improved model steam generator that is used for simulating condition in the full-scale steam generator.This model steam generator includes some heat exchanger tubes and a support tube sheet, with simulation with supervise the heat exchanger tube that comprises in the full-scale steam generator and the condition and the damaged condition of tube sheet.This model steam generator includes an evaporator shell, and housing is equipped with a feed-water inlet nozzle, is used for feedwater is imported the inside of evaporator shell; Housing is equipped with a sample heat exchanger tube at least, is used for feedwater is converted into vapor stream; Housing is equipped with a steam (vapor) outlet to be taken over, and is used for guiding vapor stream to flow out housing; Housing is equipped with a tripping device, is used for separating flowing out the water droplet of carrying secretly in the vapor stream of outlet, and this separation vessel includes many bolters, and each bolter is made of row's deflecting plate parts.
The concrete device of a kind of recommendation of Jie Shaoing here is provided with a model steam generator, and this steam generator is equipped with an improved tripping device, and the water droplet of carrying secretly in the vapor stream that is used for the model steam generator secondary side is produced is separated.This model steam generator also includes a condenser device that first group and second group condenser pipe is housed, be used for the vapor stream that the model steam generator secondary side produces is transformed back condensate water, in order to increase the adjustingization of model steam generator, a limiting valve is housed, be used for disconnecting selectively one group of condensation pipe of condenser device, the adjusting that is provided by limiting valve is than making model steam generator can accurately simulate the thermal-hydraulic condition of nuclear boiler inside in very wide operating load scope.At last, the present invention can include a feed water preheater, be used for making the feedwater of introducing steam generator secondary side to preheat a chosen temperature, so that can accurately simulate variable thermal technology's condition in each zone of tube sheet of relevant this steam generator of being supervised.Primary heater is the energy with one group of cartridge type electric resistance heater, and this well heater adopts the double-walled well heater, makes the secondary side that prevents the POLLUTION SIMULATION steam generator when one deck wall of well heater breaks.
Tripping device can include many bolters, and each bolter is made of the parallel deflecting plate parts of a row.Each deflecting plate parts is elongated, semi-cylindrical parts preferably, and it has one facing to the model steam generator secondary side concave panel that vapor stream arranges that makes progress.The upstream row steam pipe that these bolters can be arranged near steam (vapor) outlet neutralizes in the downstream row steam pipe of coupon, each deflecting plate parts of bolter in the downstream row steam pipe make the water droplet of ballistic throw plate member can flow back down in the water of model steam generator secondary side bottom horizontal by inclination.In addition, the deflecting plate parts of each bolter are with respect to the deflecting plate parts of adjacent bolter and are in tilted layout in upstream row steam pipe and downstream row steam pipe, so that give the runner that a bending is provided by the upwards vapor stream of condenser device.In the concrete device of recommending, each deflecting plate parts is miter angle with respect to the deflecting plate parts of a bolter of bolter of its top and below and is in tilted layout.
By with exemplary method with reference to the accompanying drawings the concrete device of a recommendation is described below, can more detailed understanding be arranged to the present invention, in these figure, have:
Figure 1A, 1B and 1C constitute the synoptic diagram of the improvement model steam generator of a concrete device of the present invention;
Fig. 2 A is a side cross-sectional view of evaporator of the present invention;
Fig. 2 B is the plan cross-sectional view along the evaporator of 2A B-B line;
Fig. 2 C is the partial cross section side view of a cartridge heater using in the model steam generator primary side heater assembly;
Fig. 2 D is the side cross-sectional view on evaporator primary side top;
Fig. 2 E is the plan cross-sectional view along the evaporator of E-E line among Fig. 2 A;
Fig. 2 F is the partial cross section side view of a coupon arranging in evaporator pipe sheet and the secondary side, and it has represented the riser arranged in the coupon and the end plug of sealing coupon;
Fig. 2 G is the plan cross-sectional view of the evaporator secondary side done along Fig. 2 A G-G line;
Fig. 2 H is the side cross-sectional view of tripping device in the vertical sleeve of secondary side;
Fig. 2 I is the bottom planar view that is applied in a big water droplet bolter in the tripping device of the present invention;
Fig. 2 J is the bottom planar view that is applied in a little water droplet bolter in the bolter device of the present invention;
Fig. 3 A is the schematic diagram of giving water input system that the present invention recommends;
Fig. 3 B, 3C and 3D are the schematic diagrams of giving water input system of the present invention;
Fig. 4 is the schematic diagram of model steam generator supply line;
Fig. 5 A is the mechanical arrangement side view that improves model steam generator, and how its each parts of expression steam generator is installed in framework;
Fig. 5 B is the top plan view of the steam generator mechanical arrangement done along Fig. 5 A B-B line;
Fig. 5 C is the top plan view of the steam generator mechanical arrangement done along Fig. 5 A C-C line;
Fig. 6 A transports the primary side of evaporator and the front elevation that tube sheet passes in and out the used derrick car of model steam generator main frame;
Fig. 6 B is the cross sectional side view of derrick car shown in Fig. 6 A, and how the ground jack that its expression is installed in derrick car bottom is used for adjusting the position of the primary side and the tube sheet of evaporator of the present invention.
Fig. 6 C is the top plan view of the derrick car got along Fig. 6 A C-C line;
Fig. 6 D is the top plan view of the ground jack support got along Fig. 6 A D-D line, and this ground jack is used for vertically adjusting the position of derrick car.
With reference to Figure 1A, 1B and 1C, the parts of the TYP in all figure of the same numbers among the figure, model steam generator 1 of the present invention has generally comprised: feedwater input channel 3, nourishment source 60, by the evaporator 100 that primary side 102, tube sheet 240 and secondary side 300 are formed, condenser device 400 and subcooler device 423.Feedwater input channel 3 is connected to the water supply system 600 that Fig. 3 A to 3D represents.As Fig. 5 A to 5C and Fig. 6 A to 6D represent, all critical pieces in fact all are arranged in the frame mounting 700 that includes derrick car 720, and this derrick car can make tube sheet 240 and primary side 102 shift out from the secondary side 300 of evaporator shell 100 in the pipe inspection process easily.
Carrying out heat by coupon and application boiling-heat of condensation syphonic effect principle transmits.When adopting this principle, the water of primary side 102 changes into vapor stream by heater assembly 150, this vapor stream flows to the openend of coupon 258a, 258b, 258c and 258d, and heat is sent to the feedwater of secondary side, then along the inwall of coupon 258a, 258b, 258c and 258d to dirty, flow back at last in the water of primary side 102.In order to reproduce the even heat flux distribution around the heat exchanger tube in the nuclear boiler of being supervised truly, heater assembly 150 includes correspondingly riser 270a, 270b, 270c and the 270d of coaxial arrangement in coupon 258a, 258b, 258c and 258d.As following will being described in more detail, these riseies prevent to form heat-blocking, Helmholtz (Helmhotz) instability or fluctuation in the condensate layer that the coupon inwall flows downward.These fluctuations may make produce among the heat flux distribution figure around the sample heat exchanger tube inhomogeneous, thereby cause the inexactness of simulation.Riser 270a, 270b, 270c and 270d be also by promoting the circulation in the thermosiphon principle along the downward compressed steam of coupon inwall stream, this vapor stream assists gravity that condensation flow is got back in the water of primary side 102 of evaporator 100.
The heat that is transmitted by coupon 258a, 258b, 258c and 258d makes the feedwater boiling in the secondary side and is converted into steam.In order accurately to simulate the condition in the nuclear boiler, the water droplet of carrying secretly in this steam plume must be collected and make it circular flow gets back in the secondary side, if can not collect these water droplets of carrying secretly and can not make it recycle, will increase the requirement of blowdown, and these water droplets will dilute the compound concentrations that forms sludge in secondary side 300 feedwater.The dilution meeting that generates the compound concentration of sludge is producing inexactness aspect the relative quantity of sludge accumulation between the steam generator of model steam generator and reality.Therefore, secondary side 300 includes a tripping device 355, and it is made up of many bolters, and each bolter includes the deflecting plate parts that a row is parallel to each other.As following will seeing, the scaled separation vessel of the helical blade type separation vessel of using in the separator comparison nuclear boiler that these deflecting plate parts constitute is much effective, and advantageously makes model steam generator carry out work in the real-time estimate mode.
At the outlet side of evaporator 100, model steam generator 1 includes condenser device 400.This device includes the first condenser pipe group and the second condenser pipe group 409 and 411, one electronic limiting valves 418 can selectively close the first condenser pipe group 409, so that increase effective adjusting ratio of condenser device 400.Condenser device 400 and blowdown output system 458 are connected on the subcooler device 423.Particularly, the output channel 419 of condenser device 400 is connected to the spiral pipe 424 of condensate water subcooler, and the output channel 468 of blowdown subsider 462 is connected to the blowdown subcooler spiral pipe 425 of subcooler device 423, the temperature of the circulating water that make subcooler device 423 condensate water that condenser device 400 produces and blowdown output system 458 flow out is reduced to and is lower than 200 °F, to prevent that correspondingly effluent gases brake control valve 446 and flash in 490 o'clock are fallen at condensate water and sewer.
At last, shown in Fig. 5 A to 5C and Fig. 6 A to 6D, the present invention includes framework 702 and derrick car 720 of a suspention secondary side 300.Derrick car 720 includes a spiral trigger 730, and it can make primary side 102 and tube sheet 240 carry out horizontal and vertical moving with respect to the secondary side 300 that suspends in midair, is convenient to carry out the pipe inspection more.
We consult Figure 1A and 1B particularly now, for the feedwater of secondary side 300 appointments of evaporator is depressed from entering input channel 3 for water input system 600 adding, in most of the cases, the feedwater that enters input channel 3 will be with identical by the feedwater of using in the nuclear boiler of supervising, to guarantee that used chemical property does not have difference in two systems.Yet, as will be explained in more detail below, the feedwater of using in the model steam generator 1 also can be exactly from nuclear boiler come but did the feedwater of special processing with anticorrosive additive, purpose is to slow down usefulness aspect the corrosion for estimating adjuvant in heat exchanger tube 258a, 258b, 258c and the 258d of evaporator 100.In addition, also can chemically treated desalination, deaerated water introduction input channel 3 will be made, so that the effectiveness of other anticorrosive additive beyond the typical additives in the test nuclear boiler.Though do not show in these several figure, feedwater input channel 3 also may include feedwater supercharge pump 26.1, to guarantee suitable feedwater flow is transported to the secondary side 300 of evaporator 100.
The main conditioning equipment of feedwater flow that enters the secondary side 300 of evaporator 100 is not intercepting valve 5 or 7, but is positioned at the needle-valve 11 of the pneumatic control of intercepting valve 5 and 7 upstreams.The pneumatic control mechanism of needle-valve 11 is connected on the compressed air source (not shown) by air line 15.The air supply that allows to enter valve 11 pneumatic mechanisms is regulated by current-pressure converter 13, converter 13 is connected on the output module 17 of CPU (central processing unit) 21 by cable 19, the size of current that output control module 17 sends current-pressure converter 13 to depends on the electric signal that load module 23 sends, and module 23 is connected to liquid level sensor 27 by cable 25.
In general, liquid level sensor 27 is actually a differential pressure pick-up that includes an elastic diaphragm capsule, and the straingauge bridge circuit on the bellows is printed with chemical method.Liquid level difference in the secondary side 300 of evaporator 100 inwardly or outwards bends the film in the liquid level sensor 27, and then changes the Control current that flows through in the cable 25.CPU (central processing unit) is controlled by program, so that the liquid level in the secondary side 300 remains between certain limit; And survey the fluctuation of the control signal electric current that comes, regulate the needle-valve 11 of pneumatic controls by output module 17 according to load module 23.In the concrete device of recommending, the differential pressure pick-up that liquid level sensor 27(and steam generator 1 are all) includes a manifold valve 28.Needing repairing or more during emat sensor 27, manifold valve 28 can make the operator of model steam generator 1 that liquid level sensor 27 is kept apart with pressure survey pipeline 76a, 76b, thereby does not need total system is closed down.Liquid level sensor (and all differential pressure pick-ups of steam generator 1) adopts 115DP-3-E-M1 type sensor, and it is made by Rosemount (Rosemont) company in Minnesota State Minneapolis city.
The water that flows through flowmeter 29 was heated by anticipatory electric heater 31 earlier before the secondary side 300 that enters evaporator by pipeline 58.Primary heater 31 general purposes are accurately to simulate the thermal technology's condition that feeds water in the selected district of the nuclear boiler of being supervised.If we consider not same district feedwater thermal technology condition on every side of actual nuclear boiler tube sheet, it is very clear that above-mentioned functions will become.In nuclear boiler, feedwater is flowing through the shell of secondary side than cold state, and along with its flows to the center that extends to the outer U-shaped set of heat exchange tubes of steam generator tube sheet, it is more and more hotter to become.Therefore, the thermoflux of feedwater depends on that partly the particular radial of its relative evaporator pipe sheet, this thermoflux depend on that also whether feedwater go up or " cold section " (pipeline section of process when nuclear adds hot water and leaves the evaporator secondary side) passes through from " hot arc " (promptly nuclear adds the pipeline section that hot water enters the evaporator secondary side) of heat exchanger tube.So,, then must reappear the environment temperature of this part feedwater if the thermal technology's condition around the nuclear boiler tube sheet given zone needs accurately simulation.Heat is the promoting factor of corrosion process around the heat exchanger tube, and feed temperature any inaccurate will cause the inaccurate of corrosion rate in the coupon in evaporator 100 secondary sides 300.And, because the environment temperature exponent function relation of corrosion rate and feedwater, even the very little inaccuracy of feed temperature also will cause the very mistake of corrosive pipeline speed.Primary heater 31 can make model steam generator 1 can accurately reappear in the nuclear boiler of being supervised along the corrosion rate in the selected arbitrarily heat exchanger tube of distinguishing of tube sheet by the feedwater that flows into evaporator 100 secondary sides 300 being carried out temperature control accurately.
The magnitude of current that flows through cartridge heater 40 is regulated by silicon controlled rectifier (or SCR) 44.The output of SCR 44 is connected to the input lead of cartridge heater 40 by power cable 42, the input of SCR 44 is connected to 220 volts of three-phase alternating-current supplies by power cable 46, the grid of SCR 44 is connected to the output module 50 of CPU (central processing unit) 21 by cable 48, the magnitude of current that output module 50 produces is controlled by the electric current that load module 52 produces, load module 52 is connected to the output of thermopair 344 by cable 54, and this thermopair is arranged in the feedwater in evaporator 100 secondary sides.CPU (central processing unit) 21 is controlled by program, by the backfeed loop of being made up of grid cable 48, output module 50, load module 52 and thermocouple cable 54 temperature of the feedwater that flows into secondary side 300 is remained in the claimed range.In the concrete device of recommending, SCR 44(and all other the SCR that in model steam generator 1, uses) carry out wiring by zero voltage switch (rather than angle of phase displacement type switch) mode work, with the higher hamonic wave that reduces not wish to produce as far as possible, these higher hamonic waves have destructiveness for the work of model steam generator 1 electronic equipment.
We are to the makeup Water System 60 of evaporator 100 water supply now, make-up water flows to input channel 62 during beginning, it flows through manual intercepting valve 64 there, manually the intercepting valve 5 of the water supply system 3 discussed with the front of intercepting valve 64 is identical, and it usually is used for making primary side 102 and makeup Water System 60 to keep apart when motorised cut-off valves 94 is inoperative.Therefore, manual intercepting valve 64 is almost always being opened.Manually the upstream of isolation valve 64 is positive-dispacement pumps 66, is connected with non-return valve 68a and 68b at its input side and outgoing side.Water pump 66 is being power by relay 67 drive electric motor, and relay 67 is controlled by CPU (central processing unit) 21, and its control mode will be described in detail hereinafter.
The upstream of water pump 66 outlets is waterpower point of crossing 69 and 78.On these point of crossing, by opening corresponding hand valve 72 and 432, some current that water pump 66 outlets are drawn are used for the pressure survey pipeline of liquid level sensor 27,86 and 429 is started injection when steam generator 1 initial start or " water-filling stoppage in transit ".When hand valve 72 and 432 is opened, current flow to waterline 70a, 80 and 70b form waterpower point of crossing 69 and 78, flow through corresponding pressure measurement line 76a, the 90a and 430 of liquid level sensor 27,86 and 429 then.Each liquid level sensor 27,86 and 426 includes surge valve 74,84 and 434, is used for discharging termly and cleaning the inside of these equipment.
The output of compensation water pump 66 flows to the primary side 102 of evaporator 100 by manual intercepting valve 92 and electronic flowrate control valve 94.If what fault electronic flowrate control valve 94 does not have, manually intercepting valve 92 normally never cuts out.The same with the preceding motorized valve of having discussed 7, motorized valve 94 is to have the dam spherical valve of characteristic of reliable forward.The driving of valve 94 and water pump 66 is controlled by the output of the liquid level sensor 86 that works by CPU (central processing unit) 21, how to finish in order to make this control clear, all are connected to the hydraulic line of liquid level sensor and the effect of electrical cable just to need concrete understanding.
Just often, after primary side 102 starting filling being provided the suitable water yield around with the heater assembly 105 of giving primary side 102, just there is no need to introduce new water to primary side 102.When operation, the thermosiphon principle (hereinafter describing in more detail) in the primary side 102 constantly makes water pass through primary side 102 and circulates in " closed circuit " mode.Yet, if corrosion makes one among coupon 258a, 258b, 258c and the 258d to break in process of the test, can between water in the primary side 102 of evaporator 100 and the water in the secondary side 300 some leakage appear.In this case, liquid level sensor 86 can detect water level in the primary side 102 and reduces and open flowrate control valve 94 and start make-up pump 66 by the mode of having introduced in the past.The make-up water that uses in the makeup Water System 60 preferably adopts desalination, deaerated water, and this has two reasons.At first, use etching extent in the primary side 102 that this water can reduce evaporator 100 in the whole process as far as possible and the sludge deposit that may accumulate.Secondly, go if the coupon that breaks leaks in the secondary side 300 primary side 102 interior water, such water will produce minimum influence to the chemical property of water in the secondary side 300 of evaporator 100.
With reference now to Fig. 2 A,, evaporator 100 generally comprises once side 102, tube sheet 240 and secondary side 300.Primary side is equipped with heating component and is used for evaporating the water that comprises in the primary side, and sample heat exchanger tube 258a, 258b, 258c and 258d are housed in the tube sheet, and secondary side relies on the sample heat exchanger tube that stretches out tube sheet 240 to make the feedwater of water supply system 3 change steam into.
Come 2A with the aid of pictures and 1B now particularly, the appearance of primary side 102 is made up of a garden cylindrical shell 104 that has bottom 106, and bottom 106 includes a discharge orifice 113a, and its not termination has the delivery pipe joint 113b that cleans usefulness.As shown in Figure 1B, delivery pipe joint 113b is connected to the cleaning pipeline by a cleaning valve 114.12 compressed pipe assemblies (only having represented wherein 2 108a and 108b) are screwed in the hole and (are not shown in the bottom 106), the cartridge heater 160 of heater assembly 150 is housed in these compressed pipe assemblies, the dynamic cable 109 of the not termination of each cartridge heater is used for power supply is delivered to heating element in the well heater 160.As expression roughly among Figure 1B, power cable 109 is connected on 220 volts of three-phase alternating-current supplies by zero switching mode silicon controlled rectifier 110.The grid of SCR 110 is connected to the output module 111 of CPU (central processing unit) 21 by cable 112, CPU (central processing unit) 21 receives the signal of coming according to it from the thermopair 142 that is contained in primary side 102 heater assemblies 150 tops and from the power meter 146 of the power supply input cable 148 that is connected to SCR 110, opens the grid 112 of SCR 110.Normal control mode is that the boiling temperature with a water is fixed in the scope of requirement, CPU (central processing unit) 21 opens to the grid of SCR 110 to make waterborne in evaporator 100 primary sides 102 to be raised to needed degree in the above-mentioned requirements scope, and this temperature range is recorded by thermopair 142.Another kind of control mode is the fixing surface heat flux on coupon 158a, 158b, 158c and the 158d, at this moment, CPU (central processing unit) 21 will be opened the grid of SCR 110, reach by what power meter 146 recorded with the power output that produces heater assembly 150 to require numerical value.But, if CPU (central processing unit) 21 is by thermopair 169(Fig. 2 C) record cartridge heater 160 and just be operated on the too high temperature, it will connect an alarm circuit (not showing) with the announcement operator.Arrive definite going up in limited time, this alarm circuit also will cut off heater assembly 150 automatically.The coboundary of primary side bottom 106 is illustrated annular flange flange 116.
Clamping part 115 is detachably connected on the garden cylindrical shell 104 of primary side 102 bottom 106.In this clamping part 115, the upper end annular flange flange 116 of bottom 106 is close on the lower end annular flange flange 120 of primary side by sealing ring 118.Gray Lip river gram (Grayloc) type clamp 122 has an annular groove 124 that the side is tapered, and this clamp is installed the annular flange flange 116,120 of bottom 106 and primary side housing 104.The tapered side of annular groove 124 makes annular flange flange 116,120 be close to sealing ring 118 and tightly clips together, and forms pressure and fluid-tight engagement.
Clamping part 115 includes half clamp of two and half garden shapes, has only represented half clamp 122 among Fig. 2 A.But the end of each half garden shape, half clamp is the flange of erection bolt, is marked with symbol 126a, 126b for half clamp, 122 these flanges.In addition, the post bolt flange of each half clamp includes the bolt mounting holes that is aligned with each other, and is marked with symbol 128a, 128b and 130a, 130b for half clamp, 122 these holes.When the post bolt flange of two and half clamps tightly pressed together by the nut that is screwed to the bolt end, the sealing ring 118 that the tapered side of annular groove 124 makes the annular flange flange 116 of end cap paste between these two flanges with the annular flange flange 120 of a side body 104 in half clamp 122 was clipped together.
Above the clamping part 115 on the right side of primary side housing 104, be furnished with a filling orifice 132, connect through this hole and go up the makeup Water System of introducing previously 60.In the left side of primary side housing two liquid level gaging holes 133 and 134 are housed, they are connected to the pressure survey pipeline 90a and the 90b of the liquid level sensor of introducing the front 86.A threaded thermocouple hole 138 is arranged at the top near primary side housing 104, a thermopair accessory 140 is housed, the thermopair of having discussed before including 142 in the hole.Shown in Figure 1B.The output signal of thermopair is connected to the load module 143 of CPU (central processing unit) 21, and is used for controlling SCR110, and 110 pairs of quantity of power of supplying with the heater assembly 150 in the primary side 102 of SCR are regulated.The upper end of primary side housing 140 is upper, annular flanges 149 of representing among the figure.
The heater assembly of having mentioned before the inside of primary side 102 includes 150.In general, the outside of heater assembly 150 is made up of a garden cylindrical sleeve 152, and it defines the inwall of garden post housing 104 and the annular space between sleeve 152 outside surfaces.This annular space 154 plays the runner effect of condensate water, this condensate water is because the constantly generation of thermosiphon principle institute that the interaction between heater assembly 150, coupon 258a, 258b, 258c and 258d, riser 270a, 270b, 270c and 270d and downcomer 170a, 170b, 170c, 170d, 170e and the 170f forms, and flows downward along the inwall of the garden cylindrical shell 104 of primary side 102.The inside surface of sleeve has one group of perforate of aiming at mutually 158 round a pair of back up pad 156a, 156b on the plate, these holes can be seen clearly with reference to figure 2B.Back up pad 156a, 156b are used for supporting and separating many cartridge heaters 160.These well heaters can be slidably inserted in the perforate 158 of aiming at mutually in the back up pad.
Fig. 2 c has represented the concrete structure of the cartridge heater 160 of use in heater assembly 150 and the primary heater 31.Each cartridge heater 160 generally all includes the rhabdion 161 with double-wall structure 162,163.Each layer wall preferably by heating resisting metal for example inconel 800 make.Be furnished with heating element 165 in the double wall of inconel, heating element is on every side around aluminium oxide or magnesium oxide.As discuss primary heater 31 front, adopting the double-walled suprastructure in fact can reduce around heating element 165 leaks in the shell wall 162,163, leak into heating element possibility on every side, the calandria 161 that may make well heater 160 that bleeds of this water breaks, and makes the water in evaporator 100 primary sides 102 be subjected to chemical contamination.When double-walled cartridge heater 160 is applied to primary heater 31 and heater assembly 150 as the well heater of preferentially selecting for use, should be noted that double-wall structure is even more important for primary heater 31.The cartridge heater that breaks in model steam generator 1 input side can make the feedwater that enters secondary side 300 produce chemical contamination immediately, and this is the accuracy of crash simulation probably.Conversely, if the cartridge heater 160 in the primary side heater assembly 150 breaks, the then not accuracy of crash simulation of chemical side's pollution of Chan Shenging, unless one of coupon 258a, 258b, 258c and 258d break to such degree, make a large amount of water leak into secondary side 300 from primary side 102.Because it is rare such burst pipe occurring, thus the cartridge heater of solid wall can in heater assembly 150, be used, and replace the double walled cartridge heater of the recommendation of use in primary heater 31.But that recommends in both cases is to use the double walled cartridge heater.
Turn to Fig. 2 D now, the top of the sleeve 152 of heater assembly 150 is circumscribed with illustrated socket cover 172, and an annular shoulder 175 is gone up and formed to the 174 outer garden weeks that are connected on lid 172 of annular groove.The top edge of annular groove 174 and shoulder 175 and sleeve 152 is docked engagement and is fitted together with illustrated.This structure can make the top of sleeve engage with sleeve 172 reliably, and do not enlarge the Cylinder diameter of heater assembly 150, the condensate return runner that the module diameter enlarged meeting hinders is above-mentioned, limit between the inwall by the outer wall of sleeve 152 and primary side garden cylindrical shell 104.Mounting hole 176a, the 176b, 176c and the 176d that contain the mounting hole of downcomer 170a, 170b, 170c, 170d, 170e and 170f on the surface of socket cover 172 and have frustum cone tank 178a, 178b, 178c and 178d are used for installing steam funnel 180a, 180b, 180c and 180d.Downcomer 170a to 170f provides another backflow runner for the condensate water that flows downward along sample heat exchanger tube 258a, 258b, 258c and 258d inwall.
Be clear that from Fig. 2 B downcomer 170a to 170f is arranged to approximate pentagon between all cartridge heaters of heater assembly 150, wherein downcomer 170f is arranged in the center of cartridge heater 160 arrays.Downcomer is finished two special critical functions, and at first, they return the conduction that runner increases water along the condensate water of thermosiphon principle, and this is to realize by increasing the area of section that condensate water returns runner.The second, they equably direct condensed water flow through the cartridge heater array of heater assembly 150, thereby help the heat transferred that cartridge heater produces is accumulated in the water of primary side 102 bottoms.The validity in the evaporation-condensation thermosyphon circulation loop between the steam that such two functions have increased the inflow coupon 258a, the 258b258c that are produced by heater assembly 150 and 258d and the condensate water that flows back down into along the said sample inside pipe wall in the water that the primary side bottom accumulates.The increase of this validity has not only reduced the energy requirement of model steam generator 1, and flows through the life-span of improving the cartridge heater 160 of heater assembly than the volume of cold water of cartridge heater by increase.The expected life of well heater depend on the heater table surface temperature square, the therefore expected life that has prolonged cartridge heater 160 significantly than the increase of cold water flow.Funnel 180a, 180b, 180c and 180d import air rising hole pipe 270a, 270b, 270c and 270d by the steam that heater assembly 150 is produced, and steam is directed to the blind end of sample heat exchanger tube 258a, 258b, 258c and 258d by riser, equally also improved the validity of thermosiphon principle.As hereinafter will going through, riser 270a, 270b, 270c and 270d keep apart owing to it makes along coupon inwall condensate stream that flows downward and the vapor stream of upwards deriving, in thermosiphon principle, play an important role, this vapor stream that makes progress may form the heat-blocking fluctuation in the defluent condensation water layer along the coupon inwall, thereby causes the inhomogeneous characteristic of radial and axial thermoflux.
Come with reference to Figure 1B, the pressure in the primary side is regulated by pressure transducer 135 again.Pressure transducer 135 is connected on the primary side housing by pressure measurement pipeline 136.1, pressure gauge 136 also is housed on the pressure measurement pipeline 136.1, being used for the pressure that operator to steam generator 1 provides sensor 135 to record intuitively indicates, and pressure gauge 136 is connected to load module 137 by cable 137.1 on electric.Though do not show on figure, module 137 is connected to CPU (central processing unit) 21, and when sensor 135 sent out the indicator signal of overpressure condition, CPU (central processing unit) was controlled by program, disconnects the power supply of supplying with heater assembly 150.Just in case when sensor 135 was failed to the caution signal of CPU (central processing unit) generation overpressure condition, primary side 102 included a pressure export end 184, it is connected on the safety diaphragm 190 by pipeline 188 and 192.When critical overpressure condition appears in primary side 102, safety diaphragm 190 will break and from the primary side 102 released vapour pressure of evaporator 100.Pressure export end 184 also passes through manual operating valve 186 and pipeline 188 and is connected to steam output pipe road 346, vacuum source 200, compressed nitrogen source of the gas 204 and the air vent 208 of secondary side 300 respectively by valve 198,202,206 and 209.When valve 186 was opened, pressure export end 184 just can be connected to steam output pipe road 346(by valve 198 and therefore be connected to secondary side 300).When valve 186 was opened, pressure export end 184 can also be connected to vacuum source 200, be connected to the compressed nitrogen source of the gas and be connected to air vent by valve 209 by valve 206 by manual operating valve 202.Pressure gauge 203 and 207 correspondences are connected between valve 202 and its vacuum source 200 and valve 206 and the source nitrogen 204, and a back pressure regulator 210 is connected between ventilation source 208 and the ventilation valve 209, as shown in the figure.
Valve 186,198 and 206 is useful in system's initial start and " water-filling stoppage in transit " process.In water-filling stoppage in transit process, the primary side 102 of evaporator 100 is filled to suitable liquid level by makeup Water System 60, and the feedwater of secondary side 300 usefulness feedwater input channel 3 is charged to a suitable liquid level.Then, the air of primary side 102 and secondary side 300 inside falls by the nitrogen replacement of opening valve 186,198 and 206 usefulness compressed nitrogen sources of the gas 204.Back pressure regulator 210 makes in the primary side 102 back pressure in the nitrogen environments keep to such an extent that enough make in the primary side 102 state that reaches capacity of the nitrogen in the water.Valve 202 can make the operator by opening valve 202 and 186 pairs of primary sides 102 vacuumize, by opening valve 202 and 198 pairs of secondary sides 300 vacuumize.When wanting maybe essentially to purify in the primary side 102 or in the secondary side 300 environment the time, this ability that vacuumizes is useful.At last, valve 209 can make the operator make the primary side exhaust by opening valve 186 selectively, or makes the secondary side exhaust by opening valve 198.All abilities above-mentioned all are important, because these abilities can make model steam generator 1 can simulate inner all main temperature, pressure and the environmental baseline that exists of nuclear boiler of a reality in the water-filling stoppage in transit process.
Turn back to Fig. 2 A now again, the upper flange 149 of primary side 102 relies on clamping part 215 to be tightly connected with lower annular flange 219 formation of tube sheet 240.Clamping part 215 is Gray Lip river gram (Grayloc) type Pressure clamps, and it is detachably connected to tube sheet 240 with primary side 102.On structure, it all is same as previously described clamping part 115 in all respects.Particularly, clamping part 215 includes the sealing ring 217 between the lower flange 219 of a upper flange 149 that is configured in primary side 102 and tube sheet 240.In addition, it also includes the clamp of two and half garden shapes, only sees clamp 221 wherein on the figure.These two clamps include the annular groove 223 of a taper, are used for when suitable bolt is screwed to post bolt flange 225a, 225b by bolt hole 227a, 227b and 229a, 229b annular flange flange 149,219 inwardly being pasted sealing ring 217 and tightly clip together.
Tube sheet 240 itself includes a Cylinder 242, and it is circumscribed with a tube sheet and protects thermal part 244, and this heater block 244 briefly is shown among Figure 1B.Heater block 244 includes some electrical heating elements 246, and they are connected on 240 volts of single phase poaer supply cable 248a, 248b by zero switching mode silicon controlled rectifier 250.The grid of SCR250 is connected on the output module 251 of CPU (central processing unit) 21 by cable 252.CPU (central processing unit) 21 is received load module 253, will indicate the signal of heater block 244 temperature to be sent to load module 253 by thermopair 254 by cable 255.The temperature signal that CPU (central processing unit) 21 sends thermopair 154 to it compares with the predefined temperature range of program, and a control signal takes place for the grid of SCR 250,250 pairs of amount of electrical power that are added on the heating element 246 of SCR are regulated, and program is predefined to be needed in the scope so that the temperature that tube sheet is protected thermal part 244 remains on.Tube sheet protect thermal part 244 can make model steam generator 1 reappears truly in the nuclear boiler tube sheet of reality along tube sheet radially with the heat flux distribution of y direction.If do not exist tube sheet to protect thermal part 244 among the present invention, then the thermal loss of tube sheet 240 sides can make the thermoflux in the model steam generator tube sheet and be produced difference between the thermoflux of tube sheet in the nuclear boiler of supervising.
Rotate back into Fig. 2 A, the Cylinder 242 of tube sheet 240 includes 4 hole 256a, 256b, 256c and 256d, coupon 258a, the 258b, 258c and the 258d that have mentioned before being used for installing respectively.Coupon is the most handy and made by the same metal ingredient of heat exchanger tube used in the nuclear boiler secondary side of supervising, same diameter and same wall thickness.In addition, the most handy pipe close 260a in end, 260b, 260c and the 260d that are arranged in the coupon in the secondary side 300 of evaporator 100 are closed, and preferably open the coupon end that faces toward primary side 102, represent with 262a, 262b, 262c and 262d.
Top at tube sheet 240, be provided with a sludge groove 263, it be used for will by the sludge sample of fetching in the nuclear boiler of supervising be put into sample heat exchanger tube 258a, 258b, 258c and 258d around, to test the ability that this sludge causes the heat exchange tube wall erosion.Have in the bottom of sludge groove 263 that a vertical cross-section is 264, the horizontal section is 268 discharge orifice, the operator that it can make model steam generator 1 emits all water of secondary side 300 when needs carry out blowdown and put.In order to prevent that sludge from entering in the discharging cross section 264 and 268, is placed with a porous plug 266 at the top of the vertical cross-section 264 of position shown in Fig. 2 A, in the bottom of tube sheet 240.Dispose riser 270a, 270b, 270c and 270d with one heart by garden column tube joint 274a, 274b, 274c and 274d in coupon 258a, 258b, 258c and 258d, these garden column tube joints are friction fit into riser on the hydraucone that extends funnel 180a, 180b, 180c and 180d outside the socket cover 172.
Can be clear that by Fig. 2 E and 2F riser 270a, 270b, 270c and 270d concentric arrangement are in the inner whole length that also almost extends to coupon of the coupon of their correspondences.Riser 270a, 270b, 270c and the 270d arbitrary set point of y direction place in keeping coupon has uniformly radially and to play an important role aspect the thermoflux, and this is to reach by making the condensation liquid layer may run into when defluent condensation liquid layer of coupon inwall and supposition coupon are exposed in the vapor stream upwards mobile shearing be separated by to leave.As already pointed out, this shearing can make and form the heat-blocking fluctuation in the condensation liquid layer, and this can cause the out-of-flatness in the required heat flux distribution.Except condensate stream and these mobile shearings are kept apart, it should be noted that, riser 270a, 270b, form a forward pressure reduction in the annular space that in fact 270c and 270d limit between riser outer wall and coupon inwall, this forward pressure reduction is very strong in the close zone of coupon end plug, help gravity make the condensation liquid layer along above-mentioned annular space to dirty, thereby further guarantee at coupon 258a, 258b, the inwall of 258c and 258d and riser 270a, 270b, can not form fluid " film " fluctuation (Webs) between the outer wall of 270c and 270d.These riseies can also allow to adopt more much bigger coupon than the fluid system of using prior art.Particularly, these coupons 258a, 258b, 258c and 258d and length can reach 24 inches, just substantial variation can occur in the heat flux distribution figure around the coupon then.Model steam generator uses like this that the ability of long coupon can make the operator that the sample support plate is set in the secondary side of evaporator 100, and can be truly near the thermal-hydraulic condition the back up pad zone of the reproduction nuclear boiler of being supervised with reaching.
Another Gray Lip river gram (Grayloc) type clamping part 280 removably connects the lower annular flange 284 of the upper, annular flange 276 and the secondary side 300 of tube sheet, and these see too clearly in Fig. 2 A and Fig. 2 E.As the preceding clamping part of having discussed 115, this clamping part 280 includes a sealing ring 282 and two half garden clamp 286a, 286b that have conical socket 288, when bolt 296a, 296b are installed among bolt hole 292a, the 292b of post bolt flange 290a, 290b of clamp 286a, 286b and 294a, the 294b with nut, clamp just is pressed on annular flange flange 276 and 284 on the sealing ring, becomes the fluid-tight connection status.
The secondary side 300 of evaporator is made of Cylinder 302 basically.In the bottom of Cylinder, include a liquid level gaging hole 304 and a mudhole 306, a blow-off connection 308 is housed, this pipe adapter 308 and then be connected on the blow-off pipe 310 on the mudhole.For the waste removal equipment that makes model steam generator have with full-scale nuclear boiler in the same relative capacity of waste removal equipment that simulated, should carefully determine blow-off pipe 310, so that pipeline 310 usefulness during sludge in discharging sludge groove 263 is in close proximity to the usefulness of blow-off pipe in the full-scale nuclear boiler with the spacing dimension between the tube sheet 240.Feed-water inlet 315 is equipped with on the top of liquid level survey mouth 304 and blow-off connection 308, on the water supply system of having discussed before it is connected to 3.The 2nd liquid level surveyed mouthfuls 319 and is positioned on the feed-water inlet 315, and liquid level is surveyed on the pressure survey pipeline 76a and 76b that mouthfuls 304 and 319 that discussed before being connected to and liquid level sensors 27 join.On the opposite that the highest that liquid level is surveyed mouth 319 pressure is housed and surveys mouth 317.As hereinafter will discussing, pressure is surveyed mouth 317 and is connected to pressure transducer 375, and this sensor is by the pressure in the CPU (central processing unit) 21 control evaporator secondary sides 300.
On the top of secondary side 300 Cylinders 302 are annular flange flange 321, and annular flange flange 321 is connected on the annular flange flange of assembling and locking evaporator cover 324 lower ends hermetically by clamping part 330.Clamping part 330 is another Gray Lip river gram (Grayloc) type parts, and it is detachably connected to assembling and locking evaporator cover 323 upper end of secondary side 300.The clamping part of before each, having introduced 115,215 and 280, clamping part 330 includes a sealing ring, and the sealing ring is configured between the flange 325 of the flange 321 of Cylinder 302 of secondary side 300 and assembling and locking evaporator cover 323.In addition, clamping part 330 includes the half garden clamp 334 that inside has conical socket, and the effect of clamp is that annular flange flange 321 and 325 is pressed onto on the sealing ring 332, forms the pressure seal connection status.At last, each half garden clamp includes post bolt flange 338a, 338b and the bolt hole 340a, the 340b that are aligned with each other and 342a, 342b, and these bolts hole are used for installing the bolt of being furnished with nut.On the top of evaporator top cover 323, include a steam (vapor) outlet that is positioned at the center and take over 345 and thermopair installing ports 344 that the dress thermopair is used.Steam (vapor) outlet is taken over and is connected to the jet chimney 346 shown in Figure 1B.
The inside of secondary side 300 includes the vertical garden tube 348 that is generally the garden cylindricality, and the top of this garden tube is closed with a lid 365, and a funnel shaped perforate 366 is arranged on the lid, is used for that the steam plume that secondary side 300 produces is directed to steam (vapor) outlet and takes over 345.Open the lower end of vertical garden tube 348, and include 3 positioning key 350a, 350b and 350c, is used for the Cylinder of garden tube 348 is configured in one heart the inside of secondary side 300 inwalls.The bottom of vertical garden tube 348 is sealed and installed with coupon 258a258b, 258c and 258d, and the top of vertical garden tube 348 includes tripping device 355, is used for making the liquid water droplet to separate from the steam plume that secondary side 300 produces.
Turn to Fig. 2 H, 2I and 2J now, tripping device 355 includes one group big water droplet bolter 357a to 357i on the upright position shown in Fig. 2 H.Can be clear that from Fig. 2 I, each bolter among the big water droplet bolter 357a to 357i all includes 4 parallel separate deflection plate member 359, each separate deflection plate member 359 is one and half garden cylindrical parts, and the deflecting plate 359 of each big water droplet bolter 357a to 357i all has the concave flanks of oneself facing to the vapor stream that rises along vertical garden tube 348.In addition, each deflecting plate parts 359 of big water droplet bolter all approximately become 5 degree to tilt with surface level.Such inclination can make the big water droplet that collides half garden shape parts concave surface dirty along the Y of these deflecting plate parts, and drain downwards along the inwall of vertical garden tube 348, and and the feedwater of secondary side 300 bottoms mix, though all do not show in these figure, each bolter among the big water droplet bolter 357a to 357i and the bolter above it and following bolter all are offset miter angle obliquely.This inclination and offset between nine big water droplet bolter 357a to 357i can guarantee, the vapor stream with water droplets that does not bump against half garden cylindricality deflecting plate parts 359 in a certain bolter 357 must be met deflecting plate parts 359 in next piece bolter 357.The inclination and offset of each deflecting plate parts 359 of big water droplet bolter 357a to 357i is returned the vapor stream that flows away from sample heat exchanger tube 258a, 258b, 258c and 258d with a radial motion component, and this radial motion impels the big water droplet that is aggregated in cylindricality deflecting plate parts 359 bottoms, half garden to drain along the side of vertical garden tube 348 downwards.
Can know with reference to figure 2H and to see that tripping device 355 also includes one group little water droplet bolter 361a to 361k, each little water droplet bolter includes many half less garden post deflecting plate parts 363, and this can see from Fig. 2 J is clear.As the situation of deflecting plate parts 359, the concave panel of each half garden cylindricality deflecting plate parts 363 all is to arrange towards the vapor stream that comes that rises from sample heat exchanger tube 258a, 258b, 258c and 258d.Also the same with big water droplet bolter 357, each little water droplet bolter 361 becomes 45 degree deflections to arrange with the little water droplet bolter that it is being close to up and down.The all constituents that this little water droplet bolter 361 guarantees to flow through the vapor stream of tripping device 355 again for radial deflection of its contiguous bolter will be run on the concave panel of half garden cylindricality deflecting plate parts 363 of bolter 361a to 361k.This skew also will add the component motion at the oblique angle of having discussed before to the vapor stream that upwards flows through vertical garden tube, will inevitably bring favourable drainage effect simultaneously.Unique main structural difference (except little water droplet bolter includes half more garden cylindricality deflecting plate parts 363) between big water droplet bolter 357a to 357i and the little water droplet bolter 361a to 361K: 363 pairs of horizontal directions of these deflecting plate parts are not tilt, and are actually horizontally disposed.This inclination to surface level is unnecessary, strikes and is aggregated in these surperficial water droplets and move towards the wall of vertical garden tube 348 because will make along the transverse pressure of the beneath concave surface of deflecting plate parts 363.
Aspect the water droplet that separation screen banks 357a to 357i that is in tilted layout that introduces above and 361a to 361K carry secretly in separating the steam plume that rises by vertical garden tube 348 is very effective.The inventor has been found that the tripping device of being made up of these bolters 355 can almost isolate the water of all carrying secretly from this steam plume, only stays about 0.1%.A spot of like this water loss makes secondary side 300 accumulate sludge with this nuclear boiler faster rate of being supervised, because the damage by water vector in the nuclear boiler is generally about 0.25%.Sludge accumulation speed is relevant with such damage by water vector, because contain the compound of the generation sludge of dissolving in " loss " water of being taken away by steam, if when the steam that evaporator produces is dried fully, these compounds just are retained in the secondary side 300.At the separator that reduces the 2.5 efficiency-timed rates that aspect the damage by water vector of jet chimney 346, reach, can make model steam generator with real-time mode or only the blowdown speed by Adjustment System accumulate sludge with the predetermined way that greatly quickens.If the relative damage by water vector that flows out model steam generator 1 secondary side 300 is relatively greater than the damage by water vector of the nuclear boiler of being supervised, then model steam generator can not be with the sludge accumulation speed in the real-time mode model steam generator.
Forward Figure 1B and 1C now to, the vapor pressure in evaporator 100 secondary sides 300 is regulated with two kinds of different equipment.The first, under critical condition of high voltage, the inside of secondary side 300 is connected to a safety diaphragm 367 by pipeline 369.Reply safety diaphragm 367 carries out scale, make reach secondary side Cylinder 302 at vapor pressure pressure limit in the past much the time safety diaphragm just break and discharge the steam of secondary side 300 inside.Yet, mention 367 just work under very critical condition of safety diaphragm as preceding.Under normal circumstances, the pressure in the secondary side 300 is regulated with pressure transducer 375.Sensor 375 moves together with condenser device 400 and cools off the steam that flows out secondary side 300, so that reach required pressure.Pressure transducer is surveyed mouth 317 by the pressure that pressure line 377 is connected to secondary side 300, the output signal of pressure transducer 375 is received through cable 389 by load module 387, receive SPEED CONTROL OF MOTOR device 395 with the output module 391 that CPU (central processing unit) 21 is joined, this controller is by exchanging the compressor 403 that 220 volts of feed cables of three-phase 399 drive condenser device 400.The steam output pipe road 346 of evaporator 100 secondary sides 300 is connected to the condenser 407 of the condenser device of representing among the figure, condenser 407 is made up of first group of condensation pipe 409 and second group of condensation pipe 411, and the heat of two groups of condenser pipes is coupled to the air-flow by the compressor 403 of variable-speed motor controller 395 controls.The signal that receives according to pressure transducer 375, the speed of the compressor 403 of condenser device 400 will blow out more or less air, flow through first group of pipeline 409 and second group of pipeline 411 through air conduit cover 405, so that regulate the condensing rate of steam in the pipeline 346, thereby the pressure in the secondary side 300 of evaporator 100 is remained in the predefined limit.At last, should be noted that pressure gauge 379 is connected on the pressure line 377 by pressure line 381, pressure gauge 379 provides the indication directly perceived of the pressure size in the secondary side 300, can be for Systems Operator's observation.
Turn to Fig. 1 C to illustrate in greater detail the structure of condenser device 400 now.The condensate water of first group of condenser pipe 409 generation is collected by pipeline 415, and the condensate water of second group of condenser pipe 411 generation is collected by pipeline 417.Pipeline 415 and 417 converges to main condenser pipeline 419, as shown in the figure.An important feature of the present invention is to be equiped with a motorized valve 418 in first group of condensation pipe 415, and this motorized valve can make condenser device 400 both can use first group and second group of condensation pipe 409 and 411 simultaneously.Perhaps only use second group of condensation pipe 411, open or close and decide according to valve 418.Therefore, motorized valve 418 has played the limiting valve effect of some pipeline that cuts off condenser pipe 407 selectively.This point has useful consequence, has improved total adjusting ratio of condenser system 400 widely, the nuclear boiler inside vapor pressure condition in a big way that model steam generator 1 is accurately simulated supervised.
The condensate water that condenser device 400 produces finally flows into hot well 420 from main condenser pipeline 419.The outlet of hot well 420 is connected to subcooler device 423, the condensate water that this device forms condenser device 400 and cool off and discharged from the sewers that the blowdown outlet 308 of secondary side 300 is flowed out.
The condensate water that hot well 420 and 423 pairs of condenser devices 400 of subcooler device at first are discussed cools off and discharges the mode that is adopted.Hot well 420 is worked together with liquid level sensor 429, and the balance between the condensation water quantity of the condensation water quantity that maintenance condenser device 400 forms and 423 coolings of subcooler device and discharging makes that the water yield in the hot well 420 remains at about half.One side of liquid level sensor 429 is connected to hot well outlet conduit 422 by pressure line 427, opposite side is connected to condensate output transistor road 419 by pressure line 430, article two, water-pressure survey pipeline 427 and 430 all is connected to liquid level sensor 429 by a manifold valve 428, makes liquid level sensor 429 place under repair and replacing and need not close whole model steam generator easily.By measuring the differential pressure between hot well 420 both sides, liquid level sensor 429 can indicate the liquid level of hot well inside.Liquid level sensor 429 is regulated pneumatic bleed valve 446 by CPU (central processing unit) 21, thereby the liquid level in the hot well 420 is remained in the desirable scope.This control realizes in the following manner.At first, the condensate water of the output channel 422 that flows through hot well 420 is introduced in the spiral pipe 424 of subcooler, this condensate water is cooled to 200 °F at least in subcooler, to prevent to fall in discharge end " flash ".Condensation flow through supercooling goes out subcooler 424, flow into flow control valve 446 through piping 426.Liquid level sensor 429 is connected to the load module 438 of CPU (central processing unit) 21 by cable 436, and the output signal of CPU (central processing unit) 21 is connected to current-to-pressure regulator 442 these regulators flow to pneumatic flowrate control valve 446 through gas line 448 air supply by output module 440 and cable 444.CPU (central processing unit) 21 receives Signal Regulation pneumatic control valves 446 that come, expression hot well 420 interior water levels according to it from liquid level sensor 429.Cooled condensate water continues to flow to discharge launder 692(through electronic intercepting valve 450 and manually operated intercepting valve 456 and sees Fig. 3 A to 3D after flowing out flow valve 446).Motorised cut-off valves 450 is connected to CPU (central processing unit) 21 by cable 454 and receives from liquid level sensor 429 and have only some liquid levels the hot well 420 or do not have liquid level and initial steam enters into the signal of discharge tube 426, and then CPU (central processing unit) will be closed by output module 452 and cable 454 these motorised cut-off valves 450 of order.
Turn to the cooling of subcooler device now and discharge the method that sewer adopts.Sewer is discharged to the pipeline 460 from blowdown connection 308 during beginning, and then is discharged in the blowdown subsider 462.In subsider 462, provide one to form sedimental chance for fine-particle solid in the sewer at bottom land.This sediment is removed by cleaning valve 464 termly, the sewer flow that cleaning valve control is flowed out through discharge conduit 466 from the subsider bottom.Part has been removed, and sewer sedimental, that stay in the subsider 462 flows to the output channel 468 of groove and flows to the blowdown subcooler spiral pipe 425 of subcooler device 423 from subsider 462.The same with condensed fluid subcooler spiral pipe 424, the heat of blowdown subcooler spiral pipe 425 is through air conduit cover 425.1 is coupled to the compressor 425 by subcooler device 423.In the 2 cooling air streams that produce.In order to start or the water-filling stoppage in transit, the sewer that will flow through pipeline 468 is connected to nitrogen jet system 470 by injection pipe 472, and this system is controlled by manually operated operated pneumatic valve 474.In the starting or water-filling stoppage in transit process of model steam generator 1, can make nitrogen through liquid and by injection pipe 472 and enter by conduit 468 in the secondary side 300 of evaporator 100.This spraying system facility 470 can allow the operator to pass through to make the feedwater that flows to secondary side 300 saturated quickly by the bottom (rather than one deck nitrogen is only arranged on the feedwater of secondary side 300) of secondary side 300 nitrogen always.If adopt the way of on feedwater, filling one deck nitrogen, then with nitrogen make to the needed time of water saturation can be more longer.
Shown in Fig. 1 C, the blowdown subcooler spiral pipe 425 of subcooler device 423 includes three circle spiral pipes.In addition, should be noted that the air-flow that blowdown subcooler spiral pipe 425 produces near compressor 425.2.Because about 1% of the circulating water total amount that the sewer flow of process blowdown output system 458 is condenser devices 400 to be produced, so the surface cool area that three of configuration circle spiral pipes provide to blowdown flow in the blowdown subcooler spiral pipe 425.The ratio of the surface cool area that the condensate water that produces for condenser device 400 than 13 circle spiral pipes provides is greater.The spiral pipe number of turns very big with respect to the water amount of blowdown that flows through in it in the spiral pipe adds the most close compressor 425.2 of these spiral pipes, causes sewer to be cooled to approaching the temperature of environment.And can make sample drain the draining easily and easily of any exit of outlet (expression on the figure) at a plurality of samples in spiral pipe 425 downstreams like this.Sewer is cooled to be starkly lower than 212 °F, can also guarantee reliably " flash " can not take place at any point of blowdown outlet 468, this " flash " may be in blowdown connection 308 region generating pressure surges, pressure surge in this zone may make the such secondary side 300 of discharging of sewer fastly, the speed when accumulating sludge to cause model steam generator 1 no longer can accurately simulate in the nuclear boiler tube sheet near zone of being supervised.
The adjusting of flowing through the sewer total amount of blowdown output system 458 is finished by means of flowmeter 478, and this flowmeter is connected to blowdown subcooler spiral pipe 425 by pipeline 476.In the concrete device of recommending, the FMI type thermal flowmeter that flowmeter 478 adopts the thermal meter company in Pennsylvania Trevose city to make.Pneumatic flowrate variable valve 490 is regulated in the output of flowmeter 478 in the following manner.At first, the output of flowmeter 478 is sent to the load module 482 of CPU (central processing unit) 21 by cable 480, a control electric signal takes place for output module 484 in CPU (central processing unit) 21 again, this output module is connected to current-to-pressure transducer 486 by cable 488, by the current-to-pressure transducer air flowing flow in the compressed-air line 492 that is connected to flow control valve 490 is regulated then.The sewer that flows out flow control valve 490 is excreted to blowdown feeder 692(by motorised cut-off valves of all opening at ordinary times 494 and the intercepting valve of manually controlling 500 usually and represents in Fig. 3 A to Fig. 3 D) in.But, blowdown output system 458 is disconnected mutually with blowdown feeder 692, then make the motorised cut-off valves action by the output module 496 that is connected to CPU (central processing unit) 21.Output module 496 is from being a switch in fact, and the electric current in the feed cable 498 is flow through in its control.Just in case motorized valve 494 can not be worked, then, blowdown output system 458 and blowdown feeder are kept apart by Systems Operator's manual-lock intercepting valve 500.
For the temperature of the sewer of discharging to the condensate temperature that flows out condensate water subcooler spiral pipe 424 and from blowdown subcooler spiral pipe 425 is controlled, be provided with an electromotor velocity control assembly 502, by the cooling air volume of its control subcooler compressor 425.2 generation.Motor speed control assembly 502 includes a variable speed control 504, and it regulates the magnitude of power that compressor electric motor is introduced from feed cable 506.The out-put supply cable 508 of variable speed control 504 is connected to the motor of compressor 425.2, variable speed control 504 is then controlled by the control signal that CPU (central processing unit) 21 produces, and this control signal depends on the temperature that the thermopair 518 in the output channel 426 that is contained in condensate water subcooler spiral pipe 424 records.Especially, variable speed control 504 is connected to the output module 512 of CPU (central processing unit) 21 through cable 510, CPU (central processing unit) 21 also includes a load module 514, and this load module is connected to the output terminal of thermopair 518 above-mentioned by thermocouple wire.Whether the temperature that detects according to thermopair 518 is below or above the predetermined temperature range of storing in the memory of CPU (central processing unit) 21, and the motor of compressor 425.2 correspondingly changes slowlyer or more hurry up.
Before the detailed description that finishes evaporator 100, it should be noted that, each parts by evaporator form a model steam generator, this model steam generator can not only accurately be simulated the thermal-hydraulic condition of nuclear boiler inside, and, if have any important deviation between the thermal-hydraulic condition of the thermal-hydraulic condition of simulation and reality, the steam generator of simulation always tends to the error that occurs guarding.Mention as preceding, the greater efficiency of tripping device 355 causes in secondary side 300 with faster rate accumulation sludge.The characteristics that two other of evaporator 100 also forms conservative error include: flow to the elevated pressures that coupon bears in the slower feedwater speed of secondary side feedwater and the process of the test.Slower feedwater speed can be encouraged sludge accumulation and be hidden in the crack district of secondary side 300.Elevated pressures in coupon 258a, 258b, 258c and the 258d makes coupon bear 6% " tangential stress " more, and this stress is the known contribution factor that produces the pipe corrosion rate.Represent that with regard to the relevant dangerous consequences of model steam generator pipe is in than with regard to the better situation of reality, the total trend that produces conservative error is obviously favourable (pipeline breaking and the radioactive ray contact scar that are steam generator secondary side are compared with too early a little maintenance schedule).
Come now referring to Fig. 3 A, the water supply system 600 of model steam generator 1 generally is made up of three parts, include: the preceding feedwater input channel of having discussed 3 is used for feedwater from directly be directed to the primary heater 31 of model steam generator by the nuclear boiler of being supervised; One group of water receptacle 620 that is connected to feedwater piping 3 is used as to water storage container; The water source 640 of desalination, deaerated water, it is connected to water receptacle 620.Go through this three chief components and mutual relationship thereof now.
In T-shape current point of crossing 610, in the container of having mentioned before can flowing to selectively by the electric flow valve in the opening conduits 612 618 from the feedwater of water-supply source 602 620.Pipeline 612 also includes a hand valve of opening usually 616, but if can not work when wishing that feedwater flow and container 620 are kept apart at motorized valve 618, this valve can cut out.On pipeline 612, also be provided with non-return valve 614, be back in the feedwater input channel 3 to guarantee can not make the water in the groups of containers 620.Groups of containers 620 is also returned by pipeline 622 and is connected to feedwater input channel 3.Pipeline 622 is the same with pipeline 612, includes intercepting valve 626 and non-return valve 628 of a motorised cut-off valves 624, manually control.These valves all correspondingly play the same purpose of valve 618,616 and 614 in pipeline 612.Pipeline 622 is connected to feedwater input channel 3 at "T"-shaped point of crossing 630(.Also have an intercepting valve 632 to be contained in the downstream of "T"-shaped point of crossing 630, the upstream of "T"-shaped point of crossing 610, be back to water-supply source 602 to prevent the water that calm device group 620 flows out.It is very important making current that container flows out and water-supply source 602 ability of leaving of being separated by, and has different chemical property because this water that container flows out is compared with the feedwater of nuclear boiler stream.Upstream in "T"-shaped point of crossing 630, manual intercepting valve 5 and the motorised cut-off valves 7 mentioned before feedwater input channel 3 includes.Groups of containers 620 is provided with a water tank, and what the nuclear boiler that anticorrosive additive or detergent additive are supervised with quilt in this water tank came mixes to water.Will be appreciated that groups of containers is the neither one water tank also at once.Above-mentioned adjuvant desalination, deoxygenation water with water source 640 in this water tank mixed.
In order to enlarge available test and Selection in the model steam generator and a pure water source of cleaning evaporator 100 secondary sides 300 usefulness between test routine to be provided, the water source 640 of a desalination, deaerated water is connected to the groups of containers of discussing the front 620.If anti-corrosion compound is mixed in the feedwater of nuclear boiler, then the equipment at desalination, deoxygenation water source 640 can allow the operator to test not the usefulness of the other anticorrosive additive that uses at steam generator.The used water source of the makeup Water System that water source 640 preferably links to each other with evaporator 100 primary sides 102 is identical.The water source 640 of desalination, deaerated water is connected to groups of containers 620 by waterpipe 642, waterpipe 642 is connected to container conduit 645 at 644 places, "T"-shaped current point of crossing, container conduit 645 includes a non-return valve 646, a manual intercepting valve 647 and a motorised cut-off valves 648, the corresponding function that valve that these valves had been discussed before can playing in the pipeline 612 614,616 and 618 is same.The pipeline 642 that is directly connected to desalination, deoxygenation water source 640 extends to "T"-shaped waterpower point of crossing 644, and is connected to the input channel 62 of the nourishment source 60 of primary side 102 by non-return valve 650, manual intercepting valve 652 and motorised cut-off valves 654.In addition, the valve 614,616 of the pipeline 612 ditto described of the corresponding function of these valves is identical with 618 function.
Discussed before the outgoing side of water supply system 600 includes correspondingly from the output channel 426 and 476 of condensate water subcooler spiral pipe 424 and blowdown subcooler spiral pipe 425.Motorised cut-off valves of having discussed before these two pipelines also include 450,494 and the manual intercepting valve 456 and 500 of when one of motorised cut-off valves 450,494 can not be worked, doing emergent use.These output channels 426 and 476 walk abreast and are connected to illustrated output trunk line 690.Pipeline 690 is connected to stores tank 692.This storage tank is connected to a compressed nitrogen source of the gas at its top by gas pipeline 694, and in its bottom, then is connected to pumping equipment by discharge tube 695.Equipment with the topped storage tank 692 of nitrogen can make water carry out recycle when needed in system.If the feedwater in the model steam generator, is stored tank 692 because the leakage of heat exchanger tube and during by radioactive contamination in the nuclear boiler and also is provided with to radioactive water carelessness and misprints the safeguard measure of putting.
Fig. 3 B, 3C and 3D are that turbulent flows make that the fine-particle solid in the feedwater can not precipitate before feedwater enters the secondary side 300 of evaporator 100 with the another kind of concrete device of device in the maintenance above-mentioned feedwater input channel 3.
Fig. 3 B has represented this concrete device of recommending, and wherein cross-over connection has a pair of pipeline 656 and 658 on the input channel 3 in the motorised cut-off valves 606 and the downstream of manual intercepting valve 605.As shown in FIG., before this a pair of pipeline 656 and 658, another manual and electronic intercepting valve 653,655 is housed also.Pipeline 656 is preferably got about 0.21 inch of internal diameter, and pipeline 658 is preferably got about 0.313 inch of internal diameter, according to for keeping the particle matter in the feedwater in whole pipe 3, to be in the suspended state desired flow rates, in the operational process of model steam generator 1, will use pipeline 656 or 658 one.But two are not used together.For liquid stream is switched to than large-diameter pipeline 658 from lower diameter tube road 656, each root in the pipeline 656 and 658 all includes a pair of motorised cut-off valves, is respectively 657a, 657b and 659a, 659b.From lower diameter tube road 656 to than the switching of large-diameter pipeline 658 can per hour 22 pounds carry out under arbitrary numerical value in 80 pounds the flow rates per hour.Use lower diameter tube road 656 extremely continually or use and in a wider water flow rates, to keep a very high Reynolds number (surpassing 4000) than large-diameter pipeline 658.
Fig. 3 C represented to keep to feed water another the concrete device of height anti-settling turbulent flow in the input channel 3.In this concrete device, there is the single pipeline 662 of same inner diameter to be connected in parallel with input channel 3 with input channel 3, parallel pipeline 662 includes two motorized valve 664a, 664b on illustrated position.According to desired flow rates, can use one or two of pipeline 3 and 662 to use simultaneously.In this concrete device, pipeline 3 and each root pipeline of 662 all have about 0.214 inch internal diameter, can be 24 pounds of arbitrary carrying out to 80 pounds the gamut per hour per hour from using single pipe to the switching of using two pipelines.
Fig. 3 D has also represented the concrete device that another keeps feedwater input and output system 600 required turbulent flows.Wherein, single pipe 604 is housed, it is transported to the feedwater of constant rate in the secondary side 300, and this flow has substantially exceeded the needed quantity of turbulent flow in the abundant maintenance input channel 3, so that the particle matter in the feedwater will can not settle down in pipeline 3.Because this flow velocity also substantially exceeds the practicality feedwater requirement of model steam generator 1, some equipment must be set discharge this unnecessary flow, this equipment with pneumatic control valve 672 forms provide this valve arrangement with input channel 3 in the pipeline 684 that 668 places, "T"-shaped point of crossing intersect.
The flowmeter 666 that is connected to CPU (central processing unit) 21 is regulated pneumatic control valve 672 by the current-to-pressure transducer 680 that the output module 674 with CPU (central processing unit) 21 joins.When flowmeter 666 records feedwater in the secondary side 300 of evaporator 100 when requiring to raise, it will close pneumatic control valve 672, make a less confluent in the storage tank 692 that had discussed before piping 684 is discharged into "T"-shaped point of crossing 668.Conversely, if flowmeter 666 records feedwater in the secondary side 300 when requiring to reduce,, unnecessary feedwater is emitted at 668 places, "T"-shaped point of crossing and through piping 684 just it makes pneumatic control valve 672 open the aperture of needs.At last, should be noted that leading to the pipeline 684 of storing tank 692 includes a cooling spiral pipe 670 that is used for reducing feed temperature, to guarantee " flash " condition that can not occur Anywhere in leading to the pipeline of storing in the tank way 684.
Can see that from above-mentioned explanation feedwater input and output system 600 provides three kinds of different selections for the operator of model steam generator.The first, the operator can make the feedwater that directly comes from the nuclear boiler of being supervised directly enter the secondary side 300 of evaporator 100.Second, the operator can be discharged into an a selected amount of feedwater in the groups of containers 620, compound etch-proof or washing usefulness can be added in the feedwater in order to compare test, this treated feedwater be injected in the secondary side 300 of evaporator 100 through pipeline 622 with the water pump (not shown) then.The 3rd, as used adjuvant etch-proof or washing usefulness in the feedwater Central Plains of steam generator, then the operator can be from the water source 640 injects desalinations, deaerated water for container 620, and test the usefulness of another kind of alternative anticorrosive additive, or the secondary side 300 that desalination, deaerated water are introduced evaporator 100 done to clean use.
Turn to Fig. 4 now, the supply line 696 of model steam generator 1 includes a major loop isolating switch 697, be used under the current overload situation, cutting off the heating element 40,160 of feed water preheater 31, primary side heater assembly 150 and tube sheet well heater 244 and 256 power supply simultaneously, and the compressor 403 of condenser device and subcooler and 425.2 power supply.Major loop isolating switch 697 also will cut off the positive-dispacement pump 66 of makeup Water System 60 and the power supply of feedwater supercharge pump 26.1 simultaneously when the current overload condition occurring.As shown in FIG., each equipment in these equipment connects by the mains power cable of corresponding line-breaker 697.1,697.2,697.3,697.4,697.5,697.6 and 697.7 homologous rays is parallel.In addition, a plurality of contactor assembly 698 is connected in series to line-breaker 697.1 to 697.7 above-mentioned, make power supply can be switched to the compressor 403 and 425.2 of feed water preheater 31, primary side heater assembly 150, tube sheet well heater 244, condenser device and subcooler selectively, and water pump 26.1 and 66.Particularly, the heating element 160 of heater assembly 150 is connected in series to main power line by contactor assembly 698.1, and the heating element 40 and 256 of feed water preheater 31 and tube sheet well heater 244 correspondingly is connected in series to main power line through contactor assembly 698.2 and 698.3.Equally, subcooler compressor 425.2, feedwater supercharge pump 26.1 and make-up pump 66 are connected in series to mains power cable through contactor assembly 698.4,698.6 and 698.7.Exist the remarkable exception that contactor component string connection is connected for condenser device compressor 403.This special compressor 403 both can be connected in series mains power cable by contactor assembly 698.5a, also can be connected on the mains power cable in parallel by the parallel line of being made up of contactor assembly 698.5b and 698.5c.Because the compressor of condenser 403 plays the vital role of secondary side 300 internal pressures of control evaporator 100, adopt parallel line, even variable speed control 395 damages fully, can guarantee that also the motor of the compressor 403 of condenser device can be from the main power line rood to power supply.Variable speed control is regulated the power quantity that compressor 403 receives from the primary power circuit usually.As the power-supply fluctuation preventive measure may occurring in the heater line for primary side heater assembly 150, feed water preheater 31 or tube sheet well heater 244, the heating element 160,40 of these equipment and 256 and mains power cable between be connected in series with fuse assembly 699.1,699.2 and 699.3.
With reference now to Fig. 5 A, 5B and 5C,, the physical construction of model steam generator 1 arranges and includes a main frame 702 that the inside is equipped with primary heater, evaporator 100, condenser 400 and subcooler device 423.Main frame 702 includes two mounting bracket 704a, 704b, is used for suspending in midair the secondary side 300 of evaporator 100.Secondary side 300 includes two suspend flange 706a, 706b vis-a-vis, and they stretch out the side of secondary side 300, as shown in the figure.These suspend flange 706a, 706b are contained on mounting bracket 704a, the 704b with bolt 708a, 708b.The remainder of evaporator 100 is contained on the derrick car 720, and this derrick car can make primary side 102 and tube sheet 240 horizontal and vertical moving.As hereinafter will being described in more detail, this can horizontal and vertical mobile derrick car equipment, match with Gray Lip river gram (Grayloc) type clamping part 215 and 280, can be easily near coupon 258a, 258b, 258c and 258d when any corrosive pipeline off-test that model steam generator 1 may carry out.This is an important feature of the present invention, because the corrosion test of some type need be more frequently near sample heat exchanger tube 258a, 258b, 258c and 258d.
In order to provide suitable aligning to being installed between secondary side 300, tube sheet 240 and the primary side on the derrick car 720, main frame 702 includes 4 screw rod 715a, 715b, 715c and 715d, they install to such an extent that parallel with the post of framework 720 by assembly fixture 717a, 717b 717c and 717d, the upper frame 722 of derrick car includes 4 garden cylindricality sleeve pipe 724a, 724b, 724c and 724d in its corner, the threaded 715a of these sleeve pipes, 715b, 715c and 715d alignment.In derrick car 720 rolls into main frame 702 and primary side 102 and tube sheet 240 when being in appropriate location under the secondary side 300, derrick car 720 includes a ground jack 730, and this ground jack can be used to promote tube sheet 240 and primary side 102 with respect to the bottom of secondary side 300.Receive screw rod 715a, 715b, 715c and 715d as orchard shape sleeve pipe 724a, 724b, 724c and 724d, and ground jack makes tube sheet 240 and primary side 102 rise to the position that engages with secondary side, and then tube sheet 240 and secondary side 300 will suitably obtain the location.After this, bolt (not showing) can be screwed to the end of screw rod 715a, 715b, 715c and 7 715d, so that tube sheet 240 and secondary side 300 are fastened to the position of suitable aligning.Spring that the most handy disc spring or cup spring pad constitute and loading component (not shown) installed to screw rod before corresponding nut is screwed on end, so that the lower flange 284 of facing toward secondary side 300 flexiblely for the upper flange 276 of tube sheet 240 adds upward pressure, and to a certain degree " slit " is provided between these flanges, this helps suitably installing clamp assembly 280.
Fig. 6 A, 6B, 6C and 6D have represented derrick car 720, and it is used for making primary side 102 and tube sheet 240 to move on to secondary side or leave secondary side along horizontal and vertical, and secondary side is suspended at main frame 720 inside of model steam generator 1.Particularly, derrick car 720 includes a upper frame 722, by two parallel mounting bracket 723a, 723b primary side 102 is installed on this framework.As the mounting bracket 704a of secondary side 300, the situation of 704b, mounting bracket 723a, the 723b of primary side 102 is installed on entity 184 two mounting flange 725a, the 725b that face toward outward that stretch out primary side 102 with bolt.Can be clear that with reference to figure 6A and 6C two support 723a, 723b that suspend and these supports install to primary side 102 mounting means of being taked on the derrick car framework 722.
Forward the underframe 726 of derrick car 720 now to, this framework correspondingly includes 4 castor assembly 728a, 728b, 728c and 728d on its each angle.Can be clear that with reference to figure 6A and 6D, the jackscrew of having mentioned before lower frame includes 730, it is made up of a rhizoid bar 732, is meshing the ground jack collar 733 by screw thread on the screw mandrel.Screw mandrel 732 is fixedly mounted in the illustrated jack pad 734.Shown in Fig. 6 B, when the rotation of ground jack collar inhour, jackscrew 730 vertically rises the primary side and the tube sheet 240 of derrick car 720 and evaporator 100.
When needs in service were opened evaporator 100 and check coupon 258a, 258b in the tube sheet 240,258c and 258d, the operator at first unclamped Gray Lip river gram (Grayloc) type clamping part 280 that removably connects tube sheet 240 upper ends and secondary side 300 lower ends.Then, in order to withdraw from coupon 258a, 258b, 258c and 258d from secondary side and to place one can make them carry out the moving position of transversal displacement, remove the nut of threaded 715a, 715b, 715c and the engagement of 715d screw thread to the primary side 102 of evaporator 100 and tube sheet 240 with respect to secondary side 300.Make the collar 733 counterclockwise rotations two circles of jackscrew 730 then, till castor 728a, 728b, 728c and the 728d of derrick car 720 run into ground.Certainly, be by turning on all gas pipeline and the liquid line that corresponding pipe adapter disconnects make-up water and liquid level sensor.In case finish aforesaid operations, can below secondary side 300, below main frame 702, pull out primary side 102 and tube sheet 240, and be put into any position that requires.If re-assembly evaporator 100, then carry out each step operation of the unloading process introduced above conversely.
The Ref. No. identification of using among the figure
Symbol table Ref. No. figure number
6MT Y12 9 1A
7MT AO 17 1A
Input temp control (loop 2) 21 1A
The primary side liquid level is controlled 21 1A
Evaporimeter liquid level control (loop 1) 21 1A
Pressure control (loop 3) 21 1B
Tube sheet protection heater control (loop 8) 21 1B
Heat flux or primary side fluid temperature (F.T.) control (loop 7) 21 1B
Hot well liquid level control (loop 5) 21 1C
Blowdown flow control (loop 6) 21 1C
Exhaust temperature control (loop 4) 21 1C
M 26.1 4
Load 26.2 4
7MT A203 95 1A
6MT Y10 97a 1A
7MT A102 111 1B
7MT A403 143 1B
7MT A301 145 1B
Power meter WMI 146 1B
2HP loads 395 4
M 425.2 4
7MT A202 438 1C
N
2Spraying system 470 1C
Flow 478 1C
2HP loads 504 4
Claims (12)
1, an improved model steam generator that is used for simulating condition in the full-scale steam generator that has heat exchanger tube and support tube sheet, in order to simulate and supervise the heat exchanger tube that full-scale steam generator inside comprises and the condition and the damaged condition of tube sheet, this model steam generator includes an evaporator shell, this housing is equipped with: be used for feedwater is introduced a feed-water inlet nozzle of evaporator shell inside, be used for feedwater is converted to the sample heat exchanger tube (at least one) of vapor stream, vapor stream is derived the steam (vapor) outlet adapter that housing is used, and the water droplet of carrying secretly in the steam that discharge connection is flowed out is separated a tripping device of usefulness, this tripping device includes many bolters, and each bolter is made up of one group of deflecting plate parts.
2, according to the improvement model steam generator of claim 1, portion within it, the deflecting plate parts of each bolter are parallel to each other; Model steam generator includes a condenser device, and this condenser device is equipped with first group of condensation pipe and second group of condensation pipe, and they are used for the vapor stream that evaporator shell produces is converted into condensate water; This condenser device also includes an alternative equipment that cuts off one group of condensation pipe, so that increase the adjusting ratio of model steam generator.
3, according to the improvement model steam generator of claim 1, portion within it, each deflecting plate parts becomes to be arranged vertically with the vapor stream direction.
4, according to the improvement model steam generator of claim 3, portion has at least deflecting plate parts to tilt at an angle with respect to horizontal direction within it, makes the water droplet that strikes these deflecting plate parts will be back to evaporator shell inside downwards.
5, according to the improvement model steam generator of claim 1, portion within it, above-mentioned many bolters include first to be separated screen banks and separates screen banks with second; Each bolter in first group includes more deflecting plate parts than each bolter in second group.
6, according to the improvement model steam generator of claim 1, portion within it, each deflecting plate parts all is half an elongated garden cylindrical part, and they become to be arranged vertically with vapor stream, and their concave surface is basically facing to vapor stream.
7, according to the improvement model steam generator of claim 6, portion within it, the deflecting plate parts of each bolter are actually and are parallel to each other.
8, according to the improvement model steam generator of claim 7, portion within it, the deflecting plate parts of each bolter become deflection to arrange with respect to the deflecting plate parts that are adjacent bolter, so that crooked runner is provided for the steam that flows through bolter.
9, according to the improvement model steam generator of claim 1, it also includes a condenser device, and this condenser device has first group of condensation pipe and second group of condensation pipe, is used for making vapor stream to be converted into condensate water.Wherein, condenser device comprises an equipment that disconnects one group of condensation pipe selectively, so that increase the adjusting ratio of model steam generator.
10, according to the improvement model steam generator of claim 1, it also includes a primary heater, be used for before feedwater enters evaporator shell, feedwater being heated to a previously selected temperature, so that simulate the tube sheet selection area condition on every side of full-scale steam generator.
11, according to the improvement model steam generator of claim 10, portion within it, primary heater includes a double walled cartridge heater at least.
12,
One is used for simulating the improvement model steam generator of nuclear boiler interior condition, so that the heat exchanger tube that supervision nuclear boiler inside comprises and the condition of tube sheet.Condenser device wherein is equipped with first group and second group of condensation pipe, is used for the vapor stream that evaporator shell produces is converted into condensate water; This condenser device also includes an equipment that disconnects one group of condensation pipe selectively, so that improve the adjusting ratio of model steam generator.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN198585106507A CN85106507A (en) | 1985-08-29 | 1985-08-29 | Improved model steam generator |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN198585106507A CN85106507A (en) | 1985-08-29 | 1985-08-29 | Improved model steam generator |
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| CN85106507A true CN85106507A (en) | 1987-03-11 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN102192820A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Secondary side circulating outlet interface module for secondary side preservice water pressure test of steam generator |
| CN102192818A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Secondary side preservice hydrostatic test secondary side hand hole interface module for steam generator |
| CN101680651B (en) * | 2007-05-17 | 2012-01-04 | 艾罗创新公司 | Immediate response steam generating system and method |
| CN104019955A (en) * | 2014-05-30 | 2014-09-03 | 西安交通大学 | Vapor-liquid two-phase flow simulating system and simulating method for tube shell type vapor generator |
| CN104749183A (en) * | 2013-12-30 | 2015-07-01 | 中核武汉核电运行技术股份有限公司 | Video inspection tool for secondary side tube plate of steam generator |
| CN106257263A (en) * | 2016-09-08 | 2016-12-28 | 中国核动力研究设计院 | A kind of test method with axial preheater steam generator and application |
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1985
- 1985-08-29 CN CN198585106507A patent/CN85106507A/en active Pending
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN101680651B (en) * | 2007-05-17 | 2012-01-04 | 艾罗创新公司 | Immediate response steam generating system and method |
| CN102192820A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Secondary side circulating outlet interface module for secondary side preservice water pressure test of steam generator |
| CN102192818A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Secondary side preservice hydrostatic test secondary side hand hole interface module for steam generator |
| CN102192818B (en) * | 2010-03-11 | 2013-05-22 | 中国核动力研究设计院 | Secondary side preservice hydrostatic test secondary side hand hole interface module for steam generator |
| CN102192820B (en) * | 2010-03-11 | 2013-05-22 | 中国核动力研究设计院 | Secondary side circulating outlet interface module for secondary side preservice water pressure test of steam generator |
| CN104749183A (en) * | 2013-12-30 | 2015-07-01 | 中核武汉核电运行技术股份有限公司 | Video inspection tool for secondary side tube plate of steam generator |
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| CN104019955A (en) * | 2014-05-30 | 2014-09-03 | 西安交通大学 | Vapor-liquid two-phase flow simulating system and simulating method for tube shell type vapor generator |
| CN106257263A (en) * | 2016-09-08 | 2016-12-28 | 中国核动力研究设计院 | A kind of test method with axial preheater steam generator and application |
| CN106257263B (en) * | 2016-09-08 | 2018-09-11 | 中国核动力研究设计院 | A kind of test method of band axial direction preheater steam generator and application |
| CN112714989A (en) * | 2018-09-18 | 2021-04-27 | 克诺尔商用车制动系统有限公司 | Power supply and method for supplying power |
| CN112714989B (en) * | 2018-09-18 | 2023-09-22 | 克诺尔商用车制动系统有限公司 | Power supply and method for supplying power |
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