CN115762822A - Heat transfer system of gas cooled reactor - Google Patents
Heat transfer system of gas cooled reactor Download PDFInfo
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- CN115762822A CN115762822A CN202211458039.9A CN202211458039A CN115762822A CN 115762822 A CN115762822 A CN 115762822A CN 202211458039 A CN202211458039 A CN 202211458039A CN 115762822 A CN115762822 A CN 115762822A
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Abstract
The invention discloses a heat transfer system of a gas cooled reactor, which comprises a pressure container, a neutron reflection tank and a heat transfer assembly, wherein the neutron reflection tank is arranged in the pressure container and is provided with a cavity, a feed inlet and a discharge outlet, the feed inlet is arranged at the top of the neutron reflection tank, the discharge outlet is arranged at the bottom of the neutron reflection tank, the feed inlet is communicated with the discharge outlet through the cavity, the neutron reflection tank is built by graphite carbon bricks, the neutron reflection tank is suitable for nuclear fission to generate heat, the heat transfer assembly comprises an annular body and a heat transfer pipe, the annular body is sleeved on the outer peripheral surface of the neutron reflection tank, at least part of the heat transfer pipe is arranged in the annular body and is suitable for introducing liquid, so that the liquid in the heat transfer pipe and the neutron reflection tank carry out heat exchange to gasify the liquid in the heat transfer pipe into steam, and helium is arranged in the annular body so as to reduce the pressure difference between the pressure outside the heat transfer pipe and the pressure in the heat transfer pipe. The heat transfer system of the gas cooled reactor provided by the embodiment of the invention has the advantages of simple structure, low cost and the like.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a heat transfer system of a gas cooled reactor.
Background
As an advanced fourth-generation nuclear reactor type technology, the gas-cooled reactor has the advantages of good safety, high efficiency, good economy, wide application and the like, can replace the traditional fossil energy, and in a nuclear power plant, the heat generated by the high-temperature gas-cooled reactor pushes a steam turbine to generate electricity and do work through steam.
In the related art, the heat transfer system of the gas cooled reactor has a complex structure and high processing and manufacturing costs.
Disclosure of Invention
The present invention is based on the discovery and recognition by the inventors of the following facts and problems:
no matter the power size of the gas cooled reactor is composed of a pressure vessel, a hot gas guide pipe, a main helium fan and a steam generator, helium in the pressure vessel circulates under the matching of the hot gas guide pipe and the main helium fan to take away heat of the pressure vessel reactor, in addition, the pressure vessel is provided with a reactor core radial heat insulation layer to prevent heat of a reactor core in the pressure vessel from being transferred to the pressure vessel, so that the temperature of the pressure vessel is overhigh, but due to the arrangement of the reactor core radial heat insulation layer, the volume of the pressure vessel is overlarge, and the cost is high.
The present invention is directed to solving, at least in part, one of the technical problems in the related art. Therefore, the embodiment of the invention provides a cold-stack heat transfer system which is simple in structure and low in cost.
The cold stack heat transfer system of the embodiment of the invention comprises: a pressure vessel filled with helium gas; the neutron reflection tank is arranged in the pressure container and is provided with a cavity, a feed inlet and a discharge outlet, the feed inlet is arranged at the top of the neutron reflection tank, the discharge outlet is arranged at the bottom of the neutron reflection tank, the feed inlet and the discharge outlet are communicated through the cavity, helium is filled in the cavity, the neutron reflection tank is built by graphite carbon bricks, and the neutron reflection tank is suitable for nuclear fission to generate heat; the heat transfer assembly comprises an annular body and a heat transfer pipe, the annular body is arranged in the pressure container and sleeved on the outer peripheral surface of the neutron reflector tank, at least part of the heat transfer pipe is arranged in the annular body, the heat transfer pipe is suitable for introducing liquid so that the liquid in the heat transfer pipe and the neutron reflector tank can exchange heat to enable the liquid in the heat transfer pipe to be gasified into steam, and helium is filled in the annular body so as to reduce the pressure difference between the pressure outside the heat transfer pipe and the pressure in the heat transfer pipe.
The cold reactor heat transfer system provided by the embodiment of the invention is provided with the neutron reflection tank and the heat transfer assembly, so that the temperature of the reactor in the neutron reflection tank can be reduced, and compared with the related technology, the cold reactor heat transfer system omits a main helium fan, a hot gas guide pipe, a reactor core radial heat insulation layer and other equipment, reduces the construction cost of the cold reactor heat transfer system, and can be widely applied to low-power high-temperature gas cooled reactors.
In some embodiments, the heat transfer system for the gas cooled reactor further includes a first heat insulation layer and a second heat insulation layer, the first heat insulation layer is disposed in the pressure vessel and located at the top of the neutron reflector tank, the second heat insulation layer is disposed in the pressure vessel and located at the bottom of the neutron reflector tank, the first heat insulation layer is provided with a first through hole penetrating through the first heat insulation layer along the height direction of the neutron reflector tank, the first through hole is communicated with the feed port, the second heat insulation layer is provided with a second through hole penetrating through the second heat insulation layer along the height direction of the neutron reflector tank, and the second through hole is communicated with the feed port.
In some embodiments, the heat transfer tube comprises: the water feed pipe is arranged in the annular body and extends along the circumferential direction of the neutron reflection tank, and the water feed pipe is suitable for introducing liquid; the plurality of pipelines are arranged along the circumferential direction of the neutron reflection tank, extend along the height direction of the neutron reflection tank, and the lower ends of the pipelines are communicated with the water feed pipe, so that liquid flowing out of the water feed pipe flows into the pipelines to enable the liquid to flow into the water feed pipe; the gas outlet pipe is arranged in the annular body and extends along the circumferential direction of the neutron reflector tank, and the upper end of the pipeline is communicated with the gas outlet pipe so that liquid in the pipeline can flow into the gas outlet pipe after being gasified.
In some embodiments, the gas cooled reactor heat transfer system further includes a first pressure relief pipe provided on an outer peripheral surface of the pressure vessel and communicating with the annular body, and a first relief valve provided in the first pressure relief pipe so that when the pressure in the annular body is excessively high, the first relief valve opens to release the pressure in the annular body.
In some embodiments, the heat transfer system for the gas cooled reactor further includes a second pressure relief pipe provided on an outer peripheral surface of the pressure vessel and communicating with the pressure vessel, and a second safety valve provided in the second pressure relief pipe so that the second safety valve opens to release the pressure in the pressure vessel when the pressure in the pressure vessel is excessively high.
In some embodiments, the neutron reflector tank has a first cavity and a second cavity which are communicated with each other, the first cavity is arranged on the second cavity, the cross-sectional area of the first cavity is constant in the height direction of the neutron reflector tank, and the second cavity is gradually reduced in the direction far away from the first cavity.
In some embodiments, the gas cooled reactor heat transfer system further comprises a humidity monitor disposed within the annular body such that the humidity monitor detects humidity within the annular body to monitor whether water within the heat transfer tubes leaks.
In some embodiments, the gas cooled reactor heat transport system further comprises: a first pressure probe in communication with the annular body for detecting pressure within the annular body; a second pressure detector coupled to the pressure vessel to detect a pressure within the pressure vessel.
In some embodiments, the gas cooled reactor heat transfer system further comprises a temperature detector coupled to the pressure vessel to detect a temperature within the pressure vessel.
In some embodiments, a gas flow channel penetrating through the neutron reflection tank is arranged in the neutron reflection tank, one end of the gas flow channel is communicated with the cavity, and the other end of the gas flow channel is communicated with a pressure container, so that when the temperature in the cavity is too high, helium in the pressure container flows into the pressure container.
Drawings
Fig. 1 is a schematic structural diagram of a heat transfer system of a gas cooled reactor according to an embodiment of the present invention.
Fig. 2 isbase:Sub>A cross-sectional viewbase:Sub>A-base:Sub>A of fig. 1.
Reference numerals are as follows:
a gas cooled reactor heat transfer system 100;
a pressure vessel 1;
a neutron reflection tank 2; a chamber 21; a feed port 22; a discharge port 23;
a heat transfer member 3; an annular body 31; a heat transfer pipe 32; a water feed pipe 321; a conduit 322; an outlet pipe 323;
a first insulating layer 4; a second insulating layer 5; a first pressure relief tube 6; a first safety valve 7; a second pressure relief pipe 8; a second safety valve 9; a humidity monitor 10; a first pressure detector 101; a second pressure detector 102; a temperature detector 103.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings. The embodiments described below with reference to the drawings are illustrative and intended to be illustrative of the invention and are not to be construed as limiting the invention.
A heat transport system for a gas cooled reactor according to an embodiment of the present invention is described below with reference to the accompanying drawings.
As shown in fig. 1-2, a gas-cooled reactor heat transport system 100 according to an embodiment of the present invention includes a pressure vessel 1, a neutron reflection tank 2, and a heat transfer assembly 3.
The pressure vessel 1 is filled with helium gas. Specifically, the pressure vessel 1 is filled with helium gas, the pressure of which is slightly higher than the atmospheric pressure, to prevent outside air from entering the pressure vessel 1.
Specifically, as shown in fig. 1, a first feed port 22 is provided at the top of the pressure vessel 1, a first discharge port 23 is provided at the bottom of the pressure vessel 1, the neutron reflection tank 2 is provided inside the pressure vessel 1, the neutron reflection tank 2 and the pressure vessel 1 are arranged at intervals in the inside-outside direction, the feed port 22 at the top of the neutron reflection tank 2 is communicated with the first feed port 22 of the pressure vessel 1, so that materials (for example, nuclear fuel elements are spherical in shape and can be placed at the central position of the neutron reflection tank 2 to generate heat by means of nuclear reaction, and a plurality of fuel elements form a core.) flow into a cavity 21 of the neutron reflection tank 2 through the first feed port 22 of the pressure vessel 1 and the feed port 22 of the neutron reflection tank 2, so that the nuclear fuel elements undergo nuclear fission in the neutron reflection tank 2 to generate heat, and the neutron reflection tank 2 is mainly built from graphite bricks, so that the neutron reflection tank 2 can absorb neutrons scattered outwards by the core, reduce the neutron dose suffered by the internal components, and the neutron reflection tank 2 also provides support for the core, and the control rods at the neutron reflection tank 2 to facilitate the core discharge ports and the control rod. Finally, the neutron reflection tank 2 can provide heat capacity for the reactor core, and when the residual heat of the reactor core is not dissipated in time under the working condition of an accident, the graphite carbon bricks of the neutron reflection tank 2 absorb heat, so that the temperature rise amplitude of the reactor core is reduced. The neutron reflecting tank 2 is filled with helium gas, which has excellent permeability, and thus can be used for cooling the nuclear reactor in the neutron reflecting tank 2.
The heat transfer assembly 3 comprises an annular body 31 and a heat transfer pipe 32, the annular body 31 is sleeved on the outer peripheral surface of the neutron reflector tank 2, at least part of the heat transfer pipe 32 is arranged in the annular body 31, the heat transfer pipe 32 is suitable for being filled with liquid, so that the liquid in the heat transfer pipe 32 and the neutron reflector tank 2 can exchange heat to gasify the liquid in the heat transfer pipe into steam, and helium is arranged in the annular body 31 so as to reduce the pressure difference between the pressure outside the heat transfer pipe 32 and the pressure inside the heat transfer pipe 32. Specifically, as shown in fig. 1-2, the annular body 31 is a hermetically sealed annular container, the annular body 31 is disposed in the pressure vessel 1, the inner ring of the annular body 31 is fixed on the outer circumferential surface of the neutron reflector tank 2, the inner ring of the annular body 31 is attached to the outer circumferential surface of the neutron reflector tank 2, and the heat transfer pipe 32 is fixed in the annular body 31, so that the heat transfer pipe 32, the graphite carbon bricks of the neutron reflector tank 2, and the nuclear fuel elements are not directly contacted by the annular body 31, and in the event of a rupture of the heat transfer pipe 32, the leaked liquid or gas does not damage the graphite carbon bricks and the nuclear fuel elements of the neutron reflector tank 2, thereby prolonging the service life of the neutron reflector tank 2 and ensuring the reaction efficiency of the nuclear fuel elements, both ends of the heat transfer pipe 32 respectively penetrate out of the annular body 31, and one end of the heat transfer pipe 32 can be filled with liquid (e.g., water or cooling liquid), the liquid exchanges heat with heat emitted from the neutron reflector tank 2 through the heat transfer pipe 32, so that the cooling liquid absorbs heat and vaporizes and the temperature of the reactor core in the neutron reflector tank 2 is substantially reduced, and the pressure difference between the helium gas and the helium 32 is reduced.
According to the heat transfer system 100 of the gas cooled reactor, the neutron reflecting tank 2 and the heat transfer assembly 3 are arranged, so that the temperature of a nuclear reactor in the neutron reflecting tank 2 is reduced through the heat transfer assembly 3, compared with the related art, the arrangement of a hot gas guide pipe, a main helium fan and a reactor core radial heat insulation layer can be eliminated, and the configuration of a nuclear steam supply system of the high-temperature gas cooled reactor is greatly simplified. Secondly, the arrangement of the annular body 31 and the heat transfer pipe 32 can separate the heat transfer pipe 32 from the neutron reflection tank 2, prevent the heat transfer pipe 32 from breaking and damaging graphite carbon bricks and nuclear fuel elements of the neutron reflection tank 2, and prolong the service life of the gas cooled reactor heat transfer system 100, and thirdly, because the annular body 31 is filled with helium, the leakage amount and the breaking risk of the heat transfer pipe 32 are reduced, and the safety level of the heat transfer pipe 32 can be reduced from the nuclear safety level 1 to the non-safety level, so that the quantity of nuclear safety level equipment is greatly reduced, and finally, compared with the prior art, the heat transfer component 3 does not rely on the helium to transfer heat and directly absorb the heat radiated from the neutron reflection tank 2, so that the operating pressure of the pressure container 1 is also greatly reduced, and the operating cost of the cold reactor heat transfer system is reduced.
In some embodiments, the gas cooled reactor heat transfer system 100 further includes a first thermal insulation layer 4 and a second thermal insulation layer 5, the first thermal insulation layer 4 is disposed in the pressure vessel 1 and located at the top of the neutron reflector tank 2, the second thermal insulation layer 5 is disposed in the pressure vessel 1 and located at the bottom of the neutron reflector tank 2, the first thermal insulation layer 4 is provided with a first through hole penetrating through the first thermal insulation layer 4 along the height direction of the neutron reflector tank 2, the first through hole is communicated with the feed port 22, the second thermal insulation layer 5 is provided with a second through hole penetrating through the second thermal insulation layer 5 along the height direction of the neutron reflector tank 2, and the second through hole is communicated with the feed port.
Specifically, as shown in fig. 1, the first thermal insulation layer 4 is disposed in the pressure vessel 1 and located at the top of the neutron reflector tank 2, the first thermal insulation layer 4 is provided with a first through hole penetrating through the first thermal insulation layer 4 in the vertical direction, the first through hole and the feed inlet 22 of the neutron reflector tank 2 are opposite and communicated in the vertical direction, so that the material flows into the neutron reflector tank 2 through the first through hole and the feed inlet 22 of the neutron reflector tank 2, the second thermal insulation layer 5 is disposed at the bottom of the neutron reflector tank 2, the second thermal insulation layer 5 penetrates through the second through hole of the second thermal insulation layer 5 in the vertical direction, the second through hole and the discharge outlet 23 of the neutron reflector tank 2 are opposite and communicated in the vertical direction, so that the nuclear fission-processed slag flows out of the neutron reflector tank 2 through the discharge outlet 23 and the second through hole of the neutron reflector tank 2, and through the arrangement of the first thermal insulation layer 4 and the second thermal insulation layer 5, the heat of the reactor core in the neutron reflector tank 2 is prevented from being transferred to the pressure vessel 1 to cause that the temperature of the pressure vessel 1 is too high, which results in reduction of the service life of the pressure vessel 1.
In some embodiments, heat transfer tubes 32 include a service pipe 321, a conduit 322, and an outlet pipe 323.
The water feed pipe 321 is provided in the annular body 31 and extends in the circumferential direction of the neutron reflection tank 2, and the water feed pipe 321 is adapted to be filled with liquid. Specifically, as shown in fig. 1-2, the water supply pipe 321 is annular and is disposed in the annular body 31, the water supply pipe 321 is sleeved on the inner ring of the annular body 31, and the inlet of the water supply pipe 321 extends out of the annular body 31, so as to deliver liquid to the water supply pipe 321 through the inlet of the water supply pipe 321.
The plurality of pipelines 322 are located in the annular body 31, the plurality of pipelines 322 are arranged along the circumferential direction of the neutron reflector tank 2, the pipelines 322 extend along the height direction (vertical direction as shown in fig. 1) of the neutron reflector tank 2, and the lower end of the pipeline 322 is communicated with the water feed pipe 321, so that the liquid flowing out through the water feed pipe 321 flows into the pipelines 322 to make the liquid. Specifically, as shown in fig. 1-2, the pipe 322 extends in the up-down direction, the number of the pipes 322 is multiple, the multiple pipes 322 are sequentially arranged inside the annular body 31 along the circumferential direction of the annular body 31, the lower end of the pipe 322 is an inlet of the pipe 322 and is communicated with the water feed pipe 321, so that the liquid in the water feed pipe 321 flows into the pipe 322, and the liquid absorbs the heat radiated from the neutron reflector 2 through the pipe 322, so as to cool the neutron reflector 2.
The gas outlet pipe 323 is arranged in the annular body 31 and extends along the circumferential direction of the neutron reflection tank 2, and the upper end of the pipeline 322 is communicated with the gas outlet pipe 323, so that the liquid in the pipeline 322 flows into the gas outlet pipe 323 after being gasified. Specifically, as shown in fig. 1-2, the air outlet pipe 323 is annular and is disposed in the annular body 31, the air outlet pipe 323 is disposed on the inner ring of the annular body 31, an outlet of the air outlet pipe 323 extends out of the annular body 31, the air outlet pipe 323 and the water inlet pipe are disposed at an interval in the vertical direction, and an upper end of the pipe 322 is communicated with the air outlet pipe 323, so that the gasified steam in the pipe 322 flows into the air outlet pipe 323, and then flows out of the heat transfer pipe 32 through the air outlet pipe 323, and is transferred to the user to provide heat energy to the user.
In some embodiments, the gas cooled reactor heat transport system 100 further includes a first pressure detector 101 and a second pressure detector 102
The first pressure detector 101 is communicated with the annular body 31 so as to detect the pressure in the annular body 31, specifically, as shown in fig. 1, the first pressure detector 101 is arranged outside the pressure vessel 1, and the detection end of the first pressure detector 101 extends into the annular body 31, so that the pressure of helium in the annular body 31 is detected by the first pressure detector 101, when the pressure in the annular body 31 detected by the first pressure detector 101 is lower than a preset value, it indicates that liquid in the heat transfer pipe 32 may leak to a reactor core in the neutron reflector 2, and the reactor needs to be shut down, feed water is cut off, and water leakage is prevented, and operation is continued after maintenance is completed.
The second pressure detector 102 is connected to the pressure vessel 1 in order to detect the pressure inside the pressure vessel 1. Specifically, as shown in fig. 1, the second pressure detector 102 is disposed outside the pressure vessel 1, and a detection end of the second pressure detector 102 extends into the pressure vessel 1, so that the pressure in the pressure vessel 1 is detected by the second pressure detector 102, and when the pressure in the pressure vessel 1 detected by the second pressure detector is higher than a preset value, it is indicated that the reactor heat derivation in the neutron reflection tank 2 fails, measures need to be taken to ensure that a water supply and steam channel is unobstructed, and when the pressure in the pressure vessel 1 detected by the second pressure detector is lower than the preset value, it is indicated that helium in the pressure vessel 1 may leak, and helium needs to be supplemented or a cause of the leak needs to be determined.
In some embodiments, the gas-cooled reactor heat transport system 100 further includes a first pressure relief pipe 6 and a first safety valve 7, the first pressure relief pipe 6 is provided on the outer peripheral surface of the pressure vessel 1 and communicates with the annular body 31, and the first safety valve 7 is provided in the first pressure relief pipe 6 so that when the pressure in the annular body 31 is excessively high, the first safety valve 7 opens to release the pressure in the annular body 31. Therefore, when the first pressure detector 101 detects that the pressure in the annular body 31 is higher than the preset value, in order to ensure the service life of the annular body 31, the first safety valve 7 is opened, so that the helium gas in the annular body 31 is released, and the pressure in the annular body 31 is prevented from being too high and damaged.
In some embodiments, the gas-cooled reactor heat transfer system 100 further includes a second pressure relief pipe 8 and a second safety valve 9, the second pressure relief pipe 8 is provided on the outer peripheral surface of the pressure vessel 1 and is communicated with the pressure vessel 1, and the second safety valve 9 is provided in the second pressure relief pipe 8, so that when the pressure in the pressure vessel 1 is too high, the second safety valve 9 is opened to release the pressure in the pressure vessel 1. Therefore, when the second pressure detector detects that the pressure in the annular body 31 is higher than the preset value, in order to ensure the service life of the pressure vessel 1, the second safety valve 9 is opened, so that the helium gas in the pressure vessel 1 is released, and the pressure in the pressure vessel 1 is prevented from being damaged due to overhigh pressure.
In some embodiments, the neutron reflector tank 2 has a first cavity and a second cavity that are communicated with each other, the first cavity is provided on the second cavity, the cross-sectional area of the first cavity is constant in the height direction of the neutron reflector tank 2, and the second cavity gradually decreases in the direction away from the first cavity. Specifically, as shown in fig. 1, the first cavity is arranged above the second cavity, the cross-sectional area of the first cavity is constant in the up-down direction, and the cross-sectional area of the second cavity is gradually reduced from top to bottom, in other words, the second cavity can be in a conical cylinder shape, so that the material slag in the neutron reflector 2 is prevented from being accumulated in the neutron reflector 2 outside the neutron reflector 2 in a complete discharge manner, and the design of the neutron reflector 2 is more reasonable.
In some embodiments, the gas cooled reactor heat transfer system 100 further comprises a humidity monitor 10, and the humidity monitor 10 is disposed in the annular body 31, so that the humidity monitor 10 detects the humidity in the annular body 31 to monitor whether water in the heat transfer pipe 32 leaks. Specifically, as shown in fig. 1, the humidity monitor 10 is disposed outside the pressure vessel 1, and the detecting end of the humidity detector extends into the annular body 31, so as to detect the humidity inside the annular body 31 through the humidity detector, and when the humidity inside the annular body 31 detected by the humidity detector is lower than a preset value, it indicates that the heat transfer pipe 32 has a water leakage condition, and the heat transfer pipe 32 needs to be overhauled.
In some embodiments, the gas cooled reactor heat transfer system 100 further includes a temperature detector 103 connected to the pressure vessel 1 for detecting a temperature within the pressure vessel 1. Specifically, as shown in fig. 1, the temperature detector 103 is arranged outside the pressure vessel 1, and the detection end of the temperature detector 103 extends into the pressure vessel 1, so that the temperature in the pressure vessel 1 is detected by the temperature detector 103, and then the temperature of the reactor core, the temperature of the graphite carbon brick and the temperature of the wall surface of the pressure vessel 1 can be detected, when the temperature detected by the temperature detector 103 is greater than a preset value, it is described that the reactor heat in the neutron reflection tank 2 is led out to have a fault, and measures need to be taken to ensure that the water supply and the steam channel are smooth. When the temperature detected by the temperature detector 103 is lower than the preset value, it indicates that the supply water in the heat transfer pipe 32 is too much, or the reactor power in the neutron reflection tank 2 is too low, and the reason needs to be verified.
In some embodiments, a gas flow channel (not shown) is disposed in the neutron reflection tank 2 and penetrates through the neutron reflection tank 2, one end of the gas flow channel is communicated with the cavity 21, and the other end of the gas flow channel is communicated with the pressure vessel 1, so that when the temperature in the cavity 21 is too high, helium gas in the pressure vessel 1 flows into the pressure vessel 1. Specifically, be equipped with on the outer peripheral face of neutron reflector tank 2 and run through 1 airflow channel of pressure vessel along inside and outside direction, airflow channel's one end and neutron reflector tank 2's intercommunication, airflow channel's the other end and pressure vessel 1 intercommunication, when the temperature rise in the neutron reflector tank 2 leads to pressure too high, helium in the neutron reflector tank 2 will flow into in the pressure vessel 1 through airflow channel, therefore, make helium in the pressure vessel 1 and helium in the neutron reflector tank 2 can automatic cycle, not only reduce the temperature in the neutron reflector tank 2, also reduced the pressure in the neutron reflector tank 2.
Preferably, the gas flow channel may be formed between two adjacent graphite carbon bricks, so that structural changes in the graphite carbon bricks are not required, thereby reducing the manufacturing cost of the neutron reflection tank 2.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and are therefore not to be considered limiting of the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or to implicitly indicate the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; may be mechanically coupled, may be electrically coupled or may be in communication with each other; they may be directly connected or indirectly connected through intervening media, or they may be interconnected within two elements or in a relationship where two elements interact with each other unless otherwise specifically limited. The specific meanings of the above terms in the present invention can be understood according to specific situations by those of ordinary skill in the art.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "above," and "over" a second feature may be directly on or obliquely above the second feature, or simply mean that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
In the present disclosure, the terms "one embodiment," "some embodiments," "an example," "a specific example," or "some examples" and the like mean that a specific feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Moreover, various embodiments or examples and features of various embodiments or examples described in this specification can be combined and combined by one skilled in the art without being mutually inconsistent.
Although the above embodiments have been shown and described, it should be understood that they are exemplary and not intended to limit the invention, and that various changes, modifications, substitutions and alterations can be made herein by those skilled in the art without departing from the scope of the invention.
Claims (10)
1. A gas cooled reactor heat transfer system, comprising:
a pressure vessel filled with helium gas;
the neutron reflection tank is arranged in the pressure container and is provided with a cavity, a feed inlet and a discharge outlet, the feed inlet is arranged at the top of the neutron reflection tank, the discharge outlet is arranged at the bottom of the neutron reflection tank, the feed inlet and the discharge outlet are communicated through the cavity, helium is filled in the cavity, the neutron reflection tank is built by graphite carbon bricks, and the neutron reflection tank is suitable for nuclear fission to generate heat;
the heat transfer assembly comprises an annular body and a heat transfer pipe, the annular body is arranged in the pressure container and sleeved on the outer peripheral surface of the neutron reflector tank, at least part of the heat transfer pipe is arranged in the annular body, the heat transfer pipe is suitable for introducing liquid so that the liquid in the heat transfer pipe and the neutron reflector tank can exchange heat to gasify the liquid in the heat transfer pipe into steam, and helium is filled in the annular body so as to reduce the pressure difference between the pressure outside the heat transfer pipe and the pressure in the heat transfer pipe.
2. The heat transfer system for the gas cooled reactor according to claim 1, further comprising a first heat insulation layer and a second heat insulation layer, wherein the first heat insulation layer is arranged in the pressure vessel and located at the top of the neutron reflector tank, the second heat insulation layer is arranged in the pressure vessel and located at the bottom of the neutron reflector tank, the first heat insulation layer is provided with a first through hole penetrating through the first heat insulation layer along the height direction of the neutron reflector tank, the first through hole is communicated with the feed port, the second heat insulation layer is provided with a second through hole penetrating through the second heat insulation layer along the height direction of the neutron reflector tank, and the second through hole is communicated with the discharge port.
3. The heat transfer system for the gas cooled reactor of claim 1, wherein the heat transfer tubes comprise:
the water feed pipe is arranged in the annular body and extends along the circumferential direction of the neutron reflecting tank, and the water feed pipe is suitable for introducing liquid;
the plurality of pipelines are arranged along the circumferential direction of the neutron reflection tank, extend along the height direction of the neutron reflection tank, and the lower ends of the pipelines are communicated with the water feed pipe, so that liquid flowing out of the water feed pipe flows into the pipelines to enable the liquid to flow into the water feed pipe;
the gas outlet pipe is arranged in the annular body and extends along the circumferential direction of the neutron reflector tank, and the upper end of the pipeline is communicated with the gas outlet pipe so that liquid in the pipeline can flow into the gas outlet pipe after being gasified.
4. The heat transfer system for the gas cooled reactor according to claim 1, further comprising a first pressure relief pipe provided on an outer peripheral surface of the pressure vessel and communicating with the annular body, and a first relief valve provided in the first pressure relief pipe so that the first relief valve opens to release the pressure in the annular body when the pressure in the annular body is excessively high.
5. The heat transport system for the gas cooled reactor according to claim 1, further comprising a second pressure relief pipe provided on an outer peripheral surface of the pressure vessel and communicating with the pressure vessel, and a second safety valve provided in the second pressure relief pipe so as to open when the pressure in the pressure vessel is excessively high, so as to release the pressure in the pressure vessel.
6. The heat transfer system for the gas cooled reactor according to claim 1, wherein the neutron reflector tank has a first cavity and a second cavity which are communicated with each other, the first cavity is arranged on the second cavity, the cross-sectional area of the first cavity is constant in the height direction of the neutron reflector tank, and the second cavity is gradually reduced in the direction away from the first cavity.
7. The heat transfer system for the gas cooled reactor according to claim 1, further comprising a humidity monitor disposed within the annular body, such that the humidity monitor detects the humidity within the annular body to monitor whether water leaks from within the heat transfer tubes.
8. The gas-cooled reactor heat transfer system of claim 1, further comprising:
a first pressure detector in communication with the annular body for detecting pressure within the annular body;
a second pressure detector coupled to the pressure vessel to detect a pressure within the pressure vessel.
9. The heat transfer system for the gas cooled reactor of claim 1, further comprising a temperature detector connected to the pressure vessel for detecting a temperature within the pressure vessel.
10. The heat transfer system for the gas cooled reactor according to claim 1, wherein an air flow channel penetrating through the neutron reflecting tank is arranged in the neutron reflecting tank, one end of the air flow channel is communicated with the chamber, and the other end of the air flow channel is communicated with a pressure vessel, so that when the temperature in the chamber is too high, helium in the pressure vessel flows into the pressure vessel.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211458039.9A CN115762822A (en) | 2022-11-17 | 2022-11-17 | Heat transfer system of gas cooled reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211458039.9A CN115762822A (en) | 2022-11-17 | 2022-11-17 | Heat transfer system of gas cooled reactor |
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| CN115762822A true CN115762822A (en) | 2023-03-07 |
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| CN202211458039.9A Pending CN115762822A (en) | 2022-11-17 | 2022-11-17 | Heat transfer system of gas cooled reactor |
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| CN (1) | CN115762822A (en) |
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