CN109559834A - Stable-pressure device and stable-pressure device group for nuclear reactor - Google Patents

Stable-pressure device and stable-pressure device group for nuclear reactor Download PDF

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Publication number
CN109559834A
CN109559834A CN201710882152.2A CN201710882152A CN109559834A CN 109559834 A CN109559834 A CN 109559834A CN 201710882152 A CN201710882152 A CN 201710882152A CN 109559834 A CN109559834 A CN 109559834A
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CN
China
Prior art keywords
stable
pressure device
shell
water storage
storage part
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Pending
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CN201710882152.2A
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Chinese (zh)
Inventor
石洋
王含
史韵白
张鹏
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State Power Investment Group Science and Technology Research Institute Co Ltd
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State Power Investment Group Science and Technology Research Institute Co Ltd
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Priority to CN201710882152.2A priority Critical patent/CN109559834A/en
Publication of CN109559834A publication Critical patent/CN109559834A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/09Pressure regulating arrangements, i.e. pressurisers
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention discloses a kind of stable-pressure device for nuclear reactor and stable-pressure device group, the stable-pressure device for nuclear reactor includes shell, end socket, drainpipe, water storage part and multiple heating rods.Shell extends along the vertical direction and two sides are opened wide, end socket includes upper cover and lower head, upper cover is connected with the upper end of shell, and lower head is connected with the lower end of shell, and lower head is equipped with multiple mounting holes and discharge outlet, drainpipe is connected with discharge outlet, water storage part is set to the most significant end that lower head, the open upper end of water storage part, and the open side of water storage part are not less than drainpipe, multiple heating rods are arranged in shell by mounting hole, and wherein at least one heating rod is located in water storage part.Stable-pressure device according to an embodiment of the present invention for nuclear reactor can guarantee that heating rod remains not exposed in the case where major loop or stable-pressure device a large amount of dehydrations, it is damaged as caused by heating rod dry combustion method to reduce, and major loop pressure stabilizing can be maintained, use reliability is improved.

Description

Stable-pressure device and stable-pressure device group for nuclear reactor
Technical field
The present invention relates to technical field of nuclear power, more particularly, to a kind of stable-pressure device for nuclear reactor and pressure stabilizing Device group.
Background technique
In nuclear power field or the nuclear power test industrial technical fields such as field and fluid, chemical industry, it is often necessary to circuit And the pressure of system carries out stringent control, therefore is configured with stable-pressure device (such as voltage-stablizer) mostly.And it will by electrically heated rod Water is heated to saturation temperature so that major loop maintains the voltage-stablizer of saturation pressure, because its principle is simple, reliable and stable, It is widely adopted in regulator design.However since the operating condition in the fields such as nuclear power, nuclear power verification experimental verification is more complicated, because of main system Accident conditions simulation needs and the unexpected operating condition such as dehydration, cooling down may cause liquid level in voltage-stablizer and decline, with Do not occur exposed to not being flooded electrically heated rod, and then produces electricity heating rod dry combustion method operation and cause to damage, and in voltage-stablizer Losing for water also will make voltage-stablizer lose the saturated water that pressure stabilizing is relied on, this but also voltage-stablizer in the exposed situation of heating rod Under can not again to system carry out heating and pressure stabilizing so that the main system pressure controlled is out of hand, main system can not be normal Operation.
Summary of the invention
The present invention is directed at least solve one of the technical problems existing in the prior art.For this purpose, the present invention proposes a kind of use In the stable-pressure device of nuclear reactor, the stable-pressure device for nuclear reactor can be in major loop or a large amount of dehydrations of stable-pressure device In the case where guarantee that heating rod remains not exposed, damaged, and can be maintained main as caused by heating rod dry combustion method to reduce Circuit pressure stabilizing improves use reliability.
The invention also provides a kind of stable-pressure device groups for nuclear reactor.
The stable-pressure device for nuclear reactor of embodiment according to a first aspect of the present invention, including shell, end socket, draining Pipe, water storage part and multiple heating rods.The shell extends along the vertical direction and two sides are opened wide, and the end socket includes upper cover under End socket, the upper cover are connected with the upper end of the shell, and the lower head is connected with the lower end of the shell, the lower head Equipped with multiple mounting holes and discharge outlet, the drainpipe is connected with the discharge outlet, and the water storage part is set to the lower head, The open upper end of the water storage part, and the open side of the water storage part is not less than the most significant end of the drainpipe, it is multiple described plus Hot pin is arranged in the shell by the mounting hole, and heating rod described in wherein at least one is located in the water storage part.
Stable-pressure device according to an embodiment of the present invention for nuclear reactor, by the way that water storage part is arranged in stable-pressure device, By at least one heating rod setting with water storage part in and make water storage part open side be not less than drainpipe most significant end, thus So that even if the heating rod in water storage part still is able to continue heating with right under major loop or the operating condition of a large amount of dehydrations of stable-pressure device Major loop carries out pressure stabilizing, to improve the safety of nuclear reactor major loop, and can cause to damage to avoid heating rod dry combustion method It is bad, to improve the use reliability of stable-pressure device.
According to some embodiments of the present invention, the lower head is equipped with coaming plate, the peripheral wall limit of the coaming plate and the shell Make the water storage part.
Further example according to the present invention, in order to can easily be adjusted according to situations such as height of heating rod The height of coaming plate, to guarantee to be applicable in different height heating rod, the coaming plate is configured to height-adjustable structure.
In some optional examples of the invention, for convenient for manufacturing, assembling, and guarantee the water capacity in water storage part, thus Pressure stabilizing ability after improving a large amount of dehydrations of major loop, the coaming plate are formed as shroud.
In some optional examples of the invention, multiple heating rods are respectively positioned on the peripheral wall of the shroud Yu the shell In the water storage part limited.Thus, it is possible to further improve the pressure stabilizing control ability after a large amount of dehydrations of major loop.
In some optional examples of the invention, the coaming plate is equipped with control valve, and the control valve is configured to work as The stable-pressure device is opened when being in nominal situation, is closed when the stable-pressure device is in emptying operating condition.It can protect in this way It is not exposed to demonstrate,prove heating rod, while avoiding dry combustion method, allow to a certain extent water and the intracorporal water of shell in water storage part it Between mutually circulate.
In some embodiments of the invention, at least one described mounting hole is connected with installing pipe, and the heating rod is set to In the installing pipe, and the installing pipe is formed as the water storage part.It can use installing pipe storage water in this way, to form storage Water portion avoids the heating rod dry combustion method being located therein, and then leads to the voltage regulation result for damaging and influencing stable-pressure device.
In other embodiments of the invention, the drainpipe at least partially across the discharge outlet, the draining Pipe limits the water storage part between the intracorporal part of the shell and the peripheral wall of the shell.In this way, utilizing drainpipe Water storage part is formed between shell internal perisporium, both convenient for manufacture, simplifies assembly, and it is also ensured that appearance water in water storage part Amount, to guarantee the voltage stabling control for still being able to continue pressure stabilizing under major loop or a large amount of dehydration operating conditions of stable-pressure device.
Have in some embodiments in of the invention, the water storage part forms closed cavity, and the heating rod is set to the chamber In vivo, the water storage part passes through piping connection to the end socket or the shell.Split type knot is set by stable-pressure device as a result, Structure, it is possible to reduce the structure of stable-pressure device shell is changed so that after stable-pressure device emptying dehydration, have no effect on heating rod after Continuous heating work, pressure needed for maintaining stable-pressure device.
In some optional examples of the invention, the part positioned at the water storage part of the shell has sudden expansion structure. In this way, heating rod can be made to be less susceptible to exposed, and can use increase housing cross-sectional to a certain extent Product, and then increase the volume of water area at the top of heating rod.
In some optional examples of the invention, to make heating rod be easier to be submerged by water, the heating rod is vertical adds Hot pin, Horizontal Heating stick or tilting heating rod.
In some optional examples of the invention, stable-pressure device further includes water charging system, and the water charging system includes moisturizing Tank, small pump, pipeline, the replenisher tank are connected by the small pump and the pipeline with the water storage part.Thus, it is possible to Controllable moisturizing is carried out to the heating rod region of voltage-stablizer as needed so that heating rod heat for a long time it is not exposed.
The stable-pressure device group for nuclear reactor of embodiment according to a second aspect of the present invention, including what is be connected to major loop Main stable-pressure device and at least one secondary stable-pressure device being connected to the main stable-pressure device, the main stable-pressure device and pair Stable-pressure device includes: shell, and the shell is arranged in a vertical direction and two sides are opened wide;End socket, the end socket include upper cover And lower head, the upper cover are connected with the upper end of the shell, the lower head is connected with the lower end of the shell, under described End socket is equipped with multiple mounting holes and discharge outlet;Drainpipe, the drainpipe are connected with the discharge outlet;Multiple heating rods are more A heating rod is arranged in the shell by the mounting hole.
Stable-pressure device group according to an embodiment of the present invention for nuclear reactor, by the main stable-pressure device of setting and at least One secondary stable-pressure device, and secondary stable-pressure device and main stable-pressure device are interconnected, in this way, steady when being connected with major loop After pressure device emptying, remaining stable-pressure device still can be with continuous heating, and continues to stablize major loop pressure by connecting pipeline.
Additional aspect and advantage of the invention will be set forth in part in the description, and will partially become from the following description Obviously, or practice through the invention is recognized.
Detailed description of the invention
Above-mentioned and/or additional aspect of the invention and advantage will become from the description of the embodiment in conjunction with the following figures Obviously and it is readily appreciated that, in which:
Fig. 1 is the schematic diagram of the stable-pressure device according to an embodiment of the invention for nuclear reactor.
Appended drawing reference:
100: stable-pressure device;
10: shell;20: upper cover;
30: lower head;31: discharge outlet;32: mounting hole;
40: drainpipe;50: water storage part;60: heating rod;70: coaming plate.
Specific embodiment
The embodiment of the present invention is described below in detail, examples of the embodiments are shown in the accompanying drawings, wherein from beginning to end Same or similar label indicates same or similar element or element with the same or similar functions.Below with reference to attached The embodiment of figure description is exemplary, and for explaining only the invention, and is not considered as limiting the invention.
In the description of the present invention, it is to be understood that, term " center ", " longitudinal direction ", " transverse direction ", " length ", " width ", " thickness ", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom" "inner", "outside", " up time The orientation or positional relationship of the instructions such as needle ", " counterclockwise ", " axial direction ", " radial direction ", " circumferential direction " be orientation based on the figure or Positional relationship is merely for convenience of description of the present invention and simplification of the description, rather than the device or element of indication or suggestion meaning must There must be specific orientation, be constructed and operated in a specific orientation, therefore be not considered as limiting the invention.In addition, limit There is the feature of " first ", " second " to can explicitly or implicitly include one or more of the features surely.Of the invention In description, unless otherwise indicated, the meaning of " plurality " is two or more.
In the description of the present invention, it should be noted that unless otherwise clearly defined and limited, term " installation ", " phase Even ", " connection " shall be understood in a broad sense, for example, it may be being fixedly connected, may be a detachable connection, or be integrally connected;It can To be mechanical connection, it is also possible to be electrically connected;It can be directly connected, can also can be indirectly connected through an intermediary Connection inside two elements.For the ordinary skill in the art, above-mentioned term can be understood at this with concrete condition Concrete meaning in invention.
Below with reference to the accompanying drawings stable-pressure device 100 according to an embodiment of the present invention for nuclear reactor is described.
As shown in Figure 1, the stable-pressure device 100 according to an embodiment of the present invention for nuclear reactor include shell 10, end socket, Drainpipe 40, water storage part 50 and multiple heating rods 60.
Shell 10 is generally formed into tubular structure, and (up and down direction as shown in figure 1) extends along the vertical direction, in shell 10 Accommodating chamber is limited, the two sides of shell 10 are opened wide, and upside is connected with upper cover 20, and downside is connected with lower head 30, lower head 30 Equipped with multiple mounting holes 32 and for the discharge outlet 31 of draining, multiple heating rods 60 are arranged in shell 10 by mounting hole 32 Interior, discharge outlet 31 can be located at the middle part of lower head 30, and discharge outlet 31 is connected with drainpipe 40.
Water storage part 50 is set to lower head 30, and the upper end of the open upper end of water storage part 50, such water storage part 50 can be with shell Accommodating chamber conducting in 10, to guarantee under 100 dehydration operating condition of stable-pressure device, the water in water storage part 50 being capable of shape after being heated Enter accommodating chamber at steam, to realize the effect for continuing pressure stabilizing to major loop.
Furthermore the open side (i.e. upper end) of water storage part 50 is higher than the most significant end of drainpipe 40, at least one heating rod 60 is set In in water storage part 50, in this way, (i.e. stable-pressure device 100 passes through draining when major loop or stable-pressure device 100 are in a large amount of dehydration operating conditions Pipe 40 empty after) when, heating rod 60 still be able to by water storage part 50 water impregnate, thus realize continuous heating with to major loop into Row pressure stabilizing, furthermore, it is also possible to avoid heating rod 60 from causing to damage due to the exposed rear dry combustion method of a large amount of dehydrations, to improve pressure stabilizing dress Set 100 use reliability.
Stable-pressure device 100 according to an embodiment of the present invention for nuclear reactor as a result, by stable-pressure device 100 Water storage part 50 is set, by the setting of at least one heating rod 60 in water storage part 50 and the open side of water storage part 50 is not less than The most significant end of drainpipe 40, so that even if under major loop or the operating condition of a large amount of dehydrations of stable-pressure device 100, in water storage part 50 Heating rod 60 still be able to continue heating to carry out pressure stabilizing to major loop, to improve the safety of nuclear reactor major loop, and And can also be damaged to avoid 60 dry combustion method of heating rod, to improve the use reliability of stable-pressure device 100.
According to some embodiments of the present invention, lower head 30 is equipped with coaming plate 70, between coaming plate 70 and the internal perisporium of shell 10 Water storage part 50 is limited, for example, coaming plate 70 can be to be multiple, coaming plates 70 multiple in this way can be respectively between 10 internal perisporium of shell Multiple water storage parts 50 are limited, so that the heating rod 60 being mounted in water storage part 50 is mutually indepedent, even if part water storage part 50 there is leak, remaining water storage part 50 can still guarantee the lasting pressure stabilization function of stable-pressure device 100.
Further example according to the present invention, in order to can easily be adjusted according to situations such as height of heating rod 60 The height of coaming plate 70 is saved, to guarantee being applicable in different height heating rod 60, coaming plate 70 is configured to height-adjustable structure, this 70 height of coaming plate can be turned up when 60 height of heating rod of selection is higher to guarantee that heating rod 60 can be submerged by water in sample.
As shown in Figure 1, further example according to the present invention, for convenient for manufacturing, assembling, and guarantee in water storage part 50 Water capacity, to improve the pressure stabilizing ability after a large amount of dehydrations of major loop, coaming plate 70 is formed as shroud.
Some optional examples according to the present invention, multiple heating rods 60 are respectively positioned in water storage part 50, in this way, can both guarantee Pressure stabilizing control ability after 100 dehydration of stable-pressure device, and can be damaged to avoid 60 dry combustion method of heating rod, extend heating 60 service life of stick.
Some optional examples according to the present invention, coaming plate 70 are equipped with control valve, and control valve is configured to fill when pressure stabilizing Unlatching when setting 100 in nominal situation is closed when stable-pressure device 100 is in emptying operating condition.It can guarantee heating rod in this way 60 is exposed, while avoiding dry combustion method, allows the water in water storage part 50 and between the water in shell 10 to a certain extent Mutually circulation.
Other embodiments according to the present invention are connected with installing pipe at least one mounting hole 32, one of heating Stick 60 may be mounted in installing pipe, for example, installing pipe can be extended downwardly along the vertical direction of shell 10, it can also be along shell 10 vertical direction tilts down extension, in this way, installing pipe forms water storage part 50, when 100 dehydration of stable-pressure device emptying, due to Water is still stored in the water containing chamber of installing pipe, this way it is possible to avoid heating rod 60 is completely exposed and dry combustion method is caused to damage, thus Realize the lasting pressure stabilization function of stable-pressure device 100.
Other embodiment according to the present invention, drainpipe 40 is connected with discharge outlet 31 and drainpipe 40 is at least partly worn Discharge outlet 31 is crossed to enter inside shell 10, into shell 10 in form water storage between drainpipe 40 not and the internal perisporium of shell 10 Portion 50, this is, the open side height of water storage part 50 is equal with the most significant end of drainpipe 40, when 100 dehydration of stable-pressure device emptying, Heating rod 60 in water storage part 50 still may be at the soaking state of water, cause dry combustion method to be damaged so as to avoid exposed It is bad, and then realize and continue pressure stabilization function.
Other embodiment according to the present invention, water storage part 50 are formed as closed cavity, and heating rod 60 is set to water storage part 50 It is interior, and water storage part 50 by pipeline connection to end socket (such as upper cover 20 or lower head 30) or shell 10, as a result, will be steady Pressure device 100 is set as split type structure, it is possible to reduce changes to the structure of 100 shell 10 of stable-pressure device, so that when pressure stabilizing fills After setting 100 emptying dehydrations, has no effect on heating rod 60 and continue heating work, pressure needed for maintaining stable-pressure device 100.
In some examples of the invention, the part positioned at water storage part 50 of shell 10 there is cross-sectional area to increase prominent Expand structure, in this way, to a certain extent, heating rod 60 can be made to be less susceptible to exposed, and can use and increase shell 10 Cross-sectional area, and then increase the volume of 60 top water area of heating rod.
In some optional examples of the invention, heating rod 60 can be vertical heating rod 60, consequently facilitating assembly, another In some examples, heating rod 60 can be Horizontal Heating stick 60 or tilting heating rod 60, in this way, can make heating rod 60 It is easier to be submerged by water, reduces dry combustion method and generate.
In some embodiments of the invention, 60 region of heating rod is connected to external water source, passes through pump, gravity The a variety of moisturizing forms such as water filling guarantee that heating rods 60 are not exposed, in this manner it is ensured that after 100 dehydration of stable-pressure device, to its into The long-term pressure stabilizing of row.
In some optional examples of the invention, stable-pressure device 100 further includes water charging system, and water charging system is mainly by moisturizing Tank, small pump, pipeline composition, replenisher tank are connected by small pump and pipeline with water storage part 50.Thus, it is possible to right as needed 60 region of heating rod of voltage-stablizer carries out controllable moisturizing, so that heating is not exposed for a long time for heating rod 60.
In some examples of the invention, stable-pressure device 100 further includes condensate return structure, and condensate return structure Water flow can be back to the region where heating rod 60, so that heating rod 60 can maintain the longer time not exposed, in turn Generation dry combustion method is avoided to cause to damage.
100 groups of stable-pressure device for nuclear reactor of embodiment according to a second aspect of the present invention, including main stable-pressure device 100 are connected to by pipeline with main stable-pressure device 100 at least one secondary stable-pressure device 100, secondary stable-pressure device 100, main pressure stabilizing dress It sets 100 to be connected with major loop, in this way, remaining secondary stable-pressure device 100 can pass through company after main 100 dehydration of stable-pressure device emptying The pressure stabilizing of siphunculus road maintenance major loop, wherein main stable-pressure device 100 and secondary stable-pressure device 100 are including shell 10, end socket, row Water pipe 40 and multiple heating tubes.
Shell 10 is generally formed into tubular structure, and (up and down direction as shown in figure 1) extends along the vertical direction, in shell 10 Accommodating chamber is limited, the two sides of shell 10 are opened wide, and upside is connected with upper cover 20, and downside is connected with lower head 30, lower head 30 Equipped with multiple mounting holes 32 and for the discharge outlet 31 of draining, multiple heating rods 60 are arranged in shell 10 by mounting hole 32 Interior, discharge outlet 31 can be located at the middle part of lower head 30, and discharge outlet 31 is connected with drainpipe 40.
100 groups of stable-pressure device for nuclear reactor according to an embodiment of the present invention as a result, by the way that main stable-pressure device is arranged 100 and at least one secondary stable-pressure device 100, and secondary stable-pressure device 100 is interconnected with main stable-pressure device 100, this Sample, after the stable-pressure device 100 being connected with major loop empties, remaining stable-pressure device 100 still can be with continuous heating, and passes through company Continue to stablize major loop pressure in siphunculus road.
It is according to an embodiment of the present invention for the stable-pressure device 100 of nuclear reactor and 100 groups of stable-pressure device etc. and operation All be for those of ordinary skills it is known, be not detailed herein.
In the description of this specification, reference term " one embodiment ", " some embodiments ", " illustrative examples ", The description of " example ", " specific example " or " some examples " etc. means specific features described in conjunction with this embodiment or example, knot Structure, material or feature are included at least one embodiment or example of the invention.In the present specification, to above-mentioned term Schematic representation may not refer to the same embodiment or example.Moreover, specific features, structure, material or the spy of description Point can be combined in any suitable manner in any one or more of the embodiments or examples.
Although an embodiment of the present invention has been shown and described, it will be understood by those skilled in the art that: not A variety of change, modification, replacement and modification can be carried out to these embodiments in the case where being detached from the principle of the present invention and objective, this The range of invention is defined by the claims and their equivalents.

Claims (13)

1. a kind of stable-pressure device for nuclear reactor characterized by comprising
Shell, the shell extends along the vertical direction and two sides are opened wide;
End socket, the end socket include upper cover and lower head, and the upper cover is connected with the upper end of the shell, the lower head It is connected with the lower end of the shell, the lower head is equipped with multiple mounting holes and discharge outlet;
Drainpipe, the drainpipe are connected with the discharge outlet;
Water storage part, the water storage part are set to the lower head, the open upper end of the water storage part, and the open side of the water storage part Not less than the most significant end of the drainpipe;
Multiple heating rods, multiple heating rods are arranged in the shell by the mounting hole, and described in wherein at least one Heating rod is located in the water storage part.
2. the stable-pressure device according to claim 1 for nuclear reactor, which is characterized in that the lower head, which is equipped with, to be enclosed The peripheral wall of plate, the coaming plate and the shell limits the water storage part.
3. the stable-pressure device according to claim 2 for nuclear reactor, which is characterized in that the coaming plate is configured to height Spend adjustable structure.
4. the stable-pressure device according to claim 3 for nuclear reactor, which is characterized in that the coaming plate is formed as enclosing Cylinder.
5. the stable-pressure device according to claim 4 for nuclear reactor, which is characterized in that multiple equal positions of heating rod In in the water storage part that the peripheral wall of the shroud and the shell limits.
6. the stable-pressure device according to claim 2 for nuclear reactor, which is characterized in that the coaming plate is equipped with regulating valve Door, the control valve are configured to the unlatching when the stable-pressure device is in nominal situation, when the stable-pressure device is in row It is closed when empty operating condition.
7. the stable-pressure device according to claim 1 for nuclear reactor, which is characterized in that at least one described mounting hole It is connected with installing pipe, the heating rod is set in the installing pipe, and the installing pipe is formed as the water storage part.
8. the stable-pressure device according to claim 1 for nuclear reactor, which is characterized in that at least portion of the drainpipe Divide across the discharge outlet, the drainpipe limits institute between the intracorporal part of the shell and the peripheral wall of the shell State water storage part.
9. the stable-pressure device according to claim 1 for nuclear reactor, which is characterized in that the water storage part forms closing Cavity, the heating rod are set in the cavity, and the water storage part passes through piping connection to the end socket or the shell.
10. the stable-pressure device according to claim 1 to 6 for nuclear reactor, which is characterized in that the shell The part positioned at the water storage part of body has sudden expansion structure.
11. the stable-pressure device according to claim 1 to 8 for nuclear reactor, which is characterized in that described to add Hot pin is vertical heating rod, Horizontal Heating stick or tilting heating rod.
12. the stable-pressure device according to claim 1 to 8 for nuclear reactor, which is characterized in that further include Water charging system, the water charging system include replenisher tank, small pump, pipeline, and the replenisher tank passes through the small pump and described Pipeline is connected with the water storage part.
13. a kind of stable-pressure device group for nuclear reactor, which is characterized in that including the main stable-pressure device being connected to major loop, And at least one secondary stable-pressure device for being connected to the main stable-pressure device, the main stable-pressure device and secondary stable-pressure device wrap It includes:
Shell, the shell is arranged in a vertical direction and two sides are opened wide;
End socket, the end socket include upper cover and lower head, and the upper cover is connected with the upper end of the shell, the lower head It is connected with the lower end of the shell, the lower head is equipped with multiple mounting holes and discharge outlet;
Drainpipe, the drainpipe are connected with the discharge outlet;
Multiple heating rods, multiple heating rods are arranged in the shell by the mounting hole.
CN201710882152.2A 2017-09-26 2017-09-26 Stable-pressure device and stable-pressure device group for nuclear reactor Pending CN109559834A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201710882152.2A CN109559834A (en) 2017-09-26 2017-09-26 Stable-pressure device and stable-pressure device group for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201710882152.2A CN109559834A (en) 2017-09-26 2017-09-26 Stable-pressure device and stable-pressure device group for nuclear reactor

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Publication Number Publication Date
CN109559834A true CN109559834A (en) 2019-04-02

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Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5053190A (en) * 1988-04-13 1991-10-01 Rolls-Royce And Associates Limited Water cooled nuclear reactor and pressurizer assembly
CN106653100A (en) * 2016-10-17 2017-05-10 中广核研究院有限公司 Nuclear power floating platform and novel voltage stabilizer capable of inhibiting sloshing phenomenon
CN106782680A (en) * 2016-11-29 2017-05-31 中广核研究院有限公司 Suppress the new structure of sloshing phenomenon in voltage-stablizer
CN106782695A (en) * 2016-11-29 2017-05-31 中广核研究院有限公司 The pressure stabilizer that suppression is rocked

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5053190A (en) * 1988-04-13 1991-10-01 Rolls-Royce And Associates Limited Water cooled nuclear reactor and pressurizer assembly
CN106653100A (en) * 2016-10-17 2017-05-10 中广核研究院有限公司 Nuclear power floating platform and novel voltage stabilizer capable of inhibiting sloshing phenomenon
CN106782680A (en) * 2016-11-29 2017-05-31 中广核研究院有限公司 Suppress the new structure of sloshing phenomenon in voltage-stablizer
CN106782695A (en) * 2016-11-29 2017-05-31 中广核研究院有限公司 The pressure stabilizer that suppression is rocked

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