A nuclear steam supply system

Abstract

The present invention relates to a nuclear steam supply system, which comprises: a reactor; a heat exchange device, wherein a heat exchange plate is arranged in the heat exchange device, and a number of first pipes and second pipes are fixed in the heat exchange plate, wherein the first pipes and the second pipes are arranged alternately; the two ends of the first pipe extend out of the opposite sides of the heat exchange plate and are connected to the reactor; the two ends of the second pipe are used to be connected to an external waterway; and the equivalent diameters of the inner diameters of the first pipe and the second pipe are both less than five millimeters. The present invention can transfer the heat of the coolant from the first pipe to the external waterway in the second pipe through the heat exchange plate, and the heat transfer efficiency of the heat transfer through the heat exchange plate is higher than that of the heat transfer through the air, and because the equivalent diameter of the pipe is less than five millimeters, more pipes can be arranged under the same volume, and the surface area used for heat exchange is larger, which can greatly improve the efficiency of heat exchange and achieve more full utilization of nuclear energy.

Description

Technical Field

[0001] The invention relates to the field of steam generators, and in particular to a nuclear steam supply system. Background Art

[0002] At present, nuclear energy is being used more and more widely as a clean energy. In order to utilize the energy of nuclear reactions, most of the time, steam generators are used to absorb the heat generated by the nuclear reactions, and the external water is heated to form steam, thereby realizing the utilization of nuclear energy.

[0003] In the related art, in order to heat the external water flow, the high-temperature coolant flowing out of the reactor is usually introduced into the steam generator, and the heat of the coolant is transferred to the external water flow through the steam generator, thereby heating the water flow in the pipeline and finally generating steam for external use as energy.

[0004] However, the steam generators currently used in nuclear reactors are mostly in-line circular tube or spiral tube steam generators, which generally have low heat exchange efficiency and are not fully utilized for nuclear energy. Summary of the invention

[0005] An embodiment of the present invention provides a nuclear steam supply system to solve the technical problem of low heat exchange efficiency of a steam generator used in a nuclear reactor in the related art.

[0006] In a first aspect, a nuclear steam supply system is provided, which includes: a reactor; a heat exchange device, wherein a heat exchange plate is arranged in the heat exchange device, and a plurality of first pipes and second pipes are fixed in the heat exchange plate, wherein the first pipes and the second pipes are alternately arranged; two ends of the first pipe extend out of opposite sides of the heat exchange plate and are connected to the reactor; two ends of the second pipe are used to be connected to an external waterway; and the equivalent diameters of the inner diameters of the first pipe and the second pipe are both less than five millimeters.

[0007] In some embodiments, the heat exchange device is provided with a first chamber and a second chamber inside, the first chamber and the second chamber are both filled with a coolant that absorbs the heat of the reactor, and the first chamber, the heat exchange plate and the second chamber are arranged in sequence from top to bottom; the first chamber and the heat exchange plate are separated by a first diverter, the second chamber and the heat exchange plate are separated by a second diverter, and the first diverter and the second diverter are both connected to an external waterway; one end of the first pipe is connected to the first chamber, and the other end extends downward to connect to the second chamber; one end of the second pipe is connected to the first diverter, and the other end is connected to the second diverter.

[0008] In some embodiments, a cavity is formed inside the first diverter, and the cavity is used to communicate with an external waterway; the first pipe passes through the first diverter and is isolated from the cavity, and the second pipe is inserted into the first diverter and communicates with the cavity.

[0009] In some embodiments, a main pump is disposed in the first chamber, and a suction pipe is further disposed in the heat exchange device. The coolant in the reactor flows toward the first chamber along the suction pipe driven by the main pump.

[0010] In some embodiments, the suction pipe is fixed to the heat exchange plate, and one end of the suction pipe away from the first chamber extends downward to the second chamber. The extension directions of the first pipe, the second pipe and the suction pipe are parallel, and the first pipe and the second pipe are staggered around the suction pipe.

[0011] In some embodiments, the cavity of the first diverter is connected to a water outlet pipe, and an end of the water outlet pipe away from the cavity is used to be connected to a steam-water separator.

[0012] In some embodiments, the cross-sectional shape of the first pipe and the cross-sectional shape of the second pipe are mirror images of each other, and the cross-sectional shape of the first pipe is semi-elliptical.

[0013] In some embodiments, the cross section of the first pipe includes a first straight line segment and a first elliptical arc segment connected end to end with the first straight line segment, and the first straight line segment extends along the major axis direction of the first elliptical arc segment.

[0014] In some embodiments, the first pipes and the second pipes are arranged in a plurality of rows equidistantly along the extension direction of the first straight line segment; the first pipes arranged in rows and the second pipes arranged in rows are alternately arranged along a first direction; wherein the first direction is perpendicular to the extension direction of the first straight line segment, and both are perpendicular to the extension direction of the first pipes.

[0015] In some embodiments, the cross-section of the second pipe includes a second straight line segment and a second elliptical arc segment connected end to end with the second straight line segment; the second straight line segment is parallel to the first straight line segment, and the bulging direction of the semi-elliptical cross-section of the first pipe is opposite to the bulging direction of the semi-elliptical cross-section of the second pipe.

[0016] The beneficial effects brought about by the technical solution provided by the present invention include:

[0017] An embodiment of the present invention provides a nuclear steam supply system. Since the heat exchange device is connected to the reactor, the high-temperature coolant in the reactor can be guided to the first pipe, wherein the first pipe is fixed on the heat exchange plate. When the high-temperature coolant flows into the first pipe, the heat is transferred to the second pipe also fixed on the heat exchange plate through the first pipe and the heat exchange plate, so as to heat the water flow in the second pipe and realize the utilization of nuclear energy. A plurality of first pipes and a plurality of second pipes are fixed in the heat exchange plate, and the equivalent diameters of the inner diameters of the first pipe and the second pipe are both less than five millimeters, which is much smaller than the diameter of an ordinary heat exchange pipe. A larger number of first pipes and second pipes can be arranged in the heat exchange plate, so that a significant increase in the heat exchange area per unit volume can be achieved. At the same time, the heat exchange efficiency is greater than that through air heat exchange through contact heat exchange with the heat exchange plate. Therefore, the heat exchange area per unit volume is increased, and the heat exchange capacity per unit volume is greatly improved through contact heat exchange with the heat exchange plate. BRIEF DESCRIPTION OF THE DRAWINGS

[0018] In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the following briefly introduces the drawings required for use in the description of the embodiments. Obviously, the drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without creative work.

[0019] Figure 1 A schematic structural diagram of a nuclear steam supply system provided by an embodiment of the present invention;

[0020] Figure 2 for Figure 1 Schematic diagram of the cross section of AA;

[0021] Figure 3 for Figure 1 Schematic diagram of the cross section of BB.

[0022] In the figure:

[0023] 1. Reactor; 2. Heat exchange equipment; 3. Heat exchange plate; 4. First pipeline; 5. Second pipeline; 6. First diverter; 7. Second diverter; 8. First chamber; 9. Second chamber; 10. Cavity; 11. Main pump; 12. Suction pipe; 13. Cold section of main pipeline; 14. Hot section of main pipeline; 15. Water outlet pipe; 16. Water inlet pipe. DETAILED DESCRIPTION

[0024] In order to make the purpose, technical solution and advantages of the embodiments of the present invention clearer, the technical solution in the embodiments of the present invention will be clearly and completely described below in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0025] An embodiment of the present invention provides a nuclear steam supply system, which can solve the technical problem of low heat exchange efficiency of a steam generator used in a nuclear reactor in the related art.

[0026] See also Figure 1 As shown, a nuclear steam supply system provided by an embodiment of the present invention may include: a reactor 1; a heat exchange device 2, in which a heat exchange plate 3 may be provided, in which a number of first pipes 4 and second pipes 5 may be fixed, wherein the first pipes 4 and the second pipes 5 may be arranged alternately; both ends of the first pipe 4 may extend out of the opposite sides of the heat exchange plate 3 to communicate with the reactor 1; both ends of the second pipe 5 may be used to communicate with an external waterway; and the equivalent diameters of the inner diameters of the first pipe 4 and the second pipe 5 may be less than five millimeters. The heat of the reactor is introduced into the first pipe 4 through the heat exchange device 2 connected to the reactor 1. Since the first pipe 4 and the second pipe 5 are both fixed on the heat exchange plate 3, the heat of the first pipe 4 can be quickly guided to the second pipe 5 through the heat exchange plate 3. Compared with air heat transfer, the heat exchange efficiency of the heat exchange through the heat exchange plate 3 is higher. In this embodiment, the heat exchange plate 3 can be made of a material with high thermal conductivity to further improve the heat exchange efficiency between the first pipe 4 and the second pipe 5. Since both ends of the second pipe 5 are connected to the external waterway, the external waterway can be heated until the external waterway generates steam to achieve nuclear energy. The first pipe 4 and the second pipe 5 are alternately arranged. In this embodiment, the second pipe 5 is arranged on both sides of each first pipe 4. Compared with the centralized arrangement of the first pipes 4, the alternate arrangement can increase the contact area between the heat source and the cold source, thereby improving the heat exchange efficiency. The equivalent diameters of the inner diameters of the first pipe 4 and the second pipe 5 are both less than five millimeters. Compared with the conventional heat transfer water pipe, the cross-sectional diameter is thinner. More first pipes 4 and second pipes 5 can be arranged in the same cross-section. Under the same volume, the heat exchange area is greatly improved, the heat exchange rate is greatly improved, and the nuclear energy of the reactor 1 can be more effectively utilized.

[0027] See also Figure 1As shown, in some optional embodiments, the interior of the heat exchange device 2 may be provided with a first chamber 8 and a second chamber 9, and the first chamber 8 and the second chamber 9 may be filled with a coolant that absorbs the heat of the reactor 1, and the first chamber 8, the heat exchange plate 3 and the second chamber 9 may be arranged in sequence from top to bottom; the first chamber 8 and the heat exchange plate 3 may be separated by a first diverter 6, and the second chamber 9 and the heat exchange plate 3 may be separated by a second diverter 7, and the first diverter 6 and the second diverter 7 may be both connected to the external waterway; one end of the first pipe 4 may be connected to the first chamber 8, and the other end may extend downward to be connected to the second chamber 9; one end of the second pipe 5 may be connected to the first diverter 6, and the other end may be connected to the second diverter 7. That is to say, the first chamber 8, the first pipe 4 and the second chamber 9 of the heat exchange device 2 are all filled with the coolant in the reactor 1, and the heat of the coolant is directed to the first diverter 6, the second pipe 5 and the external water channel connected to the second diverter 7 through the heat exchange plate 3. In addition to being transferred to the second pipe 5 through the first pipe 4, the heat in the coolant can also be transferred to the first diverter 6 through the first chamber 8 or to the second diverter 7 from the second chamber 9. The coolant can also be isolated from the external water channel through the first diverter 6, thereby increasing the heat exchange area between the coolant and the external water channel in a limited space and improving the heat exchange efficiency.

[0028] See also Figure 1 As shown, in some optional embodiments, a cavity 10 may be formed inside the first diverter 6, and the cavity 10 may be used to communicate with an external waterway; the first pipe 4 may pass through the first diverter 6 and be isolated from the cavity 10, and the second pipe 5 may be inserted into the first diverter 6 and communicate with the cavity 10. In other words, the first pipe 4 communicates with the first chamber 8 and is isolated from the cavity 10 of the first diverter 6, while the second pipe 5 is inserted into the first diverter 6 and communicates with the cavity 10, thereby achieving the diversion effect of the first diverter 6. In this embodiment, a cavity 10 is also provided in the second diverter 7, the first pipe 4 is isolated from the cavity 10 of the second diverter 7, and the second pipe 5 communicates with the cavity 10 of the second diverter 7.

[0029] See also Figure 1 and Figure 2As shown, in some optional embodiments, a main pump 11 may be provided in the first chamber 8, and a suction pipe 12 may be provided in the heat exchange device 2. The coolant in the reactor 1 may flow to the first chamber 8 along the suction pipe 12 under the drive of the main pump 11. That is, the coolant in the reactor 1 flows to the first chamber 8 along the suction pipe 12 under the drive of the main pump 11, and then the coolant in the first chamber 8 is guided to the second chamber 9 through the first pipe 4 and finally flows back to the reactor. The main pump 11 is arranged in the first chamber 8, so that the integration of the heat exchange device 2 can be realized. There is no need to arrange a pump body outside the heat exchange device, which effectively reduces the space occupation. The coolant is introduced into the first chamber 8 through the suction pipe 12. Since the first chamber 8 is located above the second chamber 9, the coolant therein can complete the flow under the action of gravity, which reduces the number of pump bodies. In this embodiment, the rotor part of the main pump 11 is installed in the first chamber 8, and the motor and motor components of the main pump 11 can be extended upward and placed above the heat exchange device 2, which is convenient for subsequent inspection and maintenance of the motor components.

[0030] See also Figure 1 and Figure 2 As shown, in some optional embodiments, the suction pipe 12 can be fixed to the heat exchange plate 3, and one end thereof away from the first chamber 8 can extend downward to the second chamber 9, and the extension directions of the first pipe 4, the second pipe 5 and the suction pipe 12 can be parallel, and the first pipe 4 and the second pipe 5 can be arranged alternately around the suction pipe 12. That is, the coolant first flows from top to bottom along the suction pipe 12 to the main pump 11, and the suction pipe 12 is fixed on the heat exchange plate 3, and the heat of the coolant can be transferred to the first pipe 4 and the second pipe 5 arranged around it through the heat exchange plate 3. Compared with the suction pipe 12 directly connected from the outside to the first chamber 8, fixing the suction pipe 12 on the heat exchange plate 3 can further improve the heat exchange efficiency of the heat exchange device 2, wherein the suction pipe 12 is connected to the main pipe hot section 14, and the other end of the main pipe hot section 14 extends into the core of the reactor 1, and the bottom of the second chamber 9 is also connected to the main pipe cold section 13, and the coolant flows back to the lower chamber of the reactor 1 through the main pipe cold section 13.

[0031] See also Figure 1As shown, in some optional embodiments, the cavity 10 of the first diverter 6 can be connected to the water outlet pipe 15, and the end of the water outlet pipe 15 away from the cavity 10 can be used to be connected to the steam-water separator. That is to say, the external waterway flows from bottom to top into the first diverter 6 and is connected to the external steam-water separator, and qualified steam is obtained through the steam-water separator. Since the first diverter 6 is higher than the second diverter 7, the steam in the second pipe 5 will move upward under the action of the density difference. Compared with setting the water outlet pipe 15 at the second diverter 7, more qualified steam can be obtained. In addition, since the coolant flows downward, the external waterway flows upward, so that the external waterway at each height has a temperature difference with the coolant at the same height, and the heat transfer efficiency will be higher. In this embodiment, the cavity 10 of the second diverter 7 is connected with the water inlet pipe 16.

[0032] See also Figures 1 to 3 As shown, in some optional embodiments, the cross-sectional shape of the first pipe 4 and the cross-sectional shape of the second pipe 5 can be mirror images of each other, and the cross-sectional shape of the first pipe 4 can be semi-elliptical. Compared with other shapes, the semi-elliptical cross-sectional shape can be arranged more closely, and more first pipes 4 and second pipes 5 can be arranged in the same volume, thereby achieving more efficient heat exchange.

[0033] See also Figures 1 to 3 As shown, in some optional embodiments, the cross section of the first pipe 4 may include a first straight line segment and a first elliptical arc segment connected end to end with the first straight line segment, and the first straight line segment may extend along the long axis direction of the first elliptical arc segment. In other words, the straight lines of the semi-ellipse are arranged along the long axis direction of the ellipse. Compared with the semi-ellipse arranged along the short axis direction of the ellipse or other directions, the semi-ellipse surrounded by the straight line segments arranged along the long axis direction of the ellipse is a flat semi-ellipse. More semi-ellipses can be arranged along the width direction thereof, and the heat exchange efficiency is higher.

[0034] See also Figures 1 to 3 As shown, in some optional embodiments, the first pipes 4 and the second pipes 5 can be arranged in several rows at equal distances along the extension direction of the first straight line segment; the first pipes 4 arranged in a row and the second pipes 5 arranged in a row can be arranged alternately along the first direction; wherein the first direction can be perpendicular to the extension direction of the first straight line segment, and can be perpendicular to the extension direction of the first pipe 4. That is to say, the first pipes 4 and the second pipes 5 are arranged in a row in the long axis direction of the ellipse, and a row of second pipes 5 is arranged between two adjacent rows of first pipes 4. Through this arrangement, the long sides of the first pipes 4 and the second pipes 5 are close to each other, and the short sides of the same type of pipes are close to each other, which can improve the heat exchange efficiency between the first pipes 4 and the second pipes 5.

[0035] See also Figures 1 to 3As shown, in some optional embodiments, the cross section of the second pipe 5 may include a second straight line segment and a second elliptical arc segment connected end to end with the second straight line segment; the second straight line segment may be parallel to the first straight line segment, and the convex direction of the semi-elliptical cross section of the first pipe 4 may be opposite to the convex direction of the semi-elliptical cross section of the second pipe 5. In other words, the semi-elliptical shapes of the cross section of the first pipe 4 and the cross section of the second pipe 5 bulge in opposite directions, that is, the first straight line segment of the first pipe 4 is close to the second straight line segment of the second pipe 5, and the first elliptical arc segment of the first pipe 4 is close to the second elliptical arc segment of the second pipe 5, and the distance between them is smaller due to the close proximity of the straight line segments, and the heat exchange efficiency is higher.

[0036] The principle of a nuclear steam supply system provided by an embodiment of the present invention is:

[0037] By connecting the reactor 1 with the heat exchange device 2, the heat of the coolant in the reactor 1 is guided to the first pipe 4. By alternately fixing the first pipe 4 and the second pipe 5 on the heat exchange plate 3, the heat of the first pipe 4 is finally transferred to the second pipe 5 through the heat exchange plate 3. Since the heat is transferred through the heat exchange plate 3, its thermal conductivity is higher than that of air, which can improve the heat exchange efficiency. Since the equivalent diameters of the inner diameters of the first pipe 4 and the second pipe 5 are both less than five millimeters, more first pipes 4 and second pipes 5 can be arranged under equal volume, the heat exchange area is larger, and the utilization efficiency of nuclear energy is greatly improved.

[0038] In the description of the present invention, it should be noted that the terms "upper", "lower", etc. indicate positions or positional relationships based on the positions or positional relationships shown in the accompanying drawings, and are only for the convenience of describing the present invention and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific position, be constructed and operated in a specific position, and therefore cannot be understood as a limitation on the present invention. Unless otherwise clearly specified and limited, the terms "installed", "connected", and "connected" should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be a direct connection, or it can be an indirect connection through an intermediate medium, or it can be a connection between the two elements. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to the specific circumstances.

[0039] It should be noted that, in the present invention, relational terms such as "first" and "second" are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Moreover, the terms "include", "comprise" or any other variants thereof are intended to cover non-exclusive inclusion, so that a process, method, article or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, article or device. In the absence of further restrictions, the elements defined by the sentence "comprise a ..." do not exclude the existence of other identical elements in the process, method, article or device including the elements.

[0040] The foregoing is merely a specific embodiment of the present invention, which enables those skilled in the art to understand or implement the present invention. Various modifications to these embodiments will be apparent to those skilled in the art, and the general principles defined herein may be implemented in other embodiments without departing from the spirit or scope of the present invention. Therefore, the present invention will not be limited to the embodiments shown herein, but rather to the widest scope consistent with the principles and novel features claimed herein.

Claims

1. A nuclear steam supply system, characterized in that: It includes: Reactor (1); A heat exchange device (2), wherein a heat exchange plate (3) is arranged in the heat exchange device (2), and a plurality of first pipes (4) and second pipes (5) are fixed in the heat exchange plate (3), wherein the first pipes (4) and the second pipes (5) are arranged alternately; The two ends of the first pipe (4) extend out of the opposite sides of the heat exchange plate (3) and are connected to the reactor (1); the two ends of the second pipe (5) are used to be connected to an external waterway; and the equivalent diameters of the inner diameters of the first pipe (4) and the second pipe (5) are both less than five millimeters.

2. The nuclear steam supply system according to claim 1, characterized in that: The heat exchange device (2) is provided with a first chamber (8) and a second chamber (9) inside, the first chamber (8) and the second chamber (9) are both filled with a coolant for absorbing heat from the reactor (1), and the first chamber (8), the heat exchange plate (3) and the second chamber (9) are arranged in sequence from top to bottom; The first chamber (8) is separated from the heat exchange plate (3) by a first flow divider (6), the second chamber (9) is separated from the heat exchange plate (3) by a second flow divider (7), and the first flow divider (6) and the second flow divider (7) are both connected to an external waterway; One end of the first pipe (4) is in communication with the first chamber (8), and the other end extends downwardly to be in communication with the second chamber (9); One end of the second pipeline (5) is in communication with the first flow divider (6), and the other end is in communication with the second flow divider (7).

3. The nuclear steam supply system according to claim 2, characterized in that: A cavity (10) is formed inside the first flow divider (6), and the cavity (10) is used to communicate with an external waterway; The first pipe (4) passes through the first flow divider (6) and is isolated from the cavity (10), and the second pipe (5) is inserted into the first flow divider (6) and is connected to the cavity (10).

4. The nuclear steam supply system according to claim 3, characterized in that: A main pump (11) is arranged in the first chamber (8), and a suction pipe (12) is also arranged in the heat exchange device (2); the coolant in the reactor (1) flows toward the first chamber (8) along the suction pipe (12) driven by the main pump (11).

5. The nuclear steam supply system according to claim 4, characterized in that: The suction pipe (12) is fixed to the heat exchange plate (3), and one end of the suction pipe (12) away from the first chamber (8) extends downward to the second chamber (9); the extension directions of the first pipe (4), the second pipe (5) and the suction pipe (12) are parallel, and the first pipe (4) and the second pipe (5) are arranged in a staggered manner around the suction pipe (12).

6. The nuclear steam supply system according to claim 3, characterized in that: The cavity (10) of the first flow divider (6) is connected to a water outlet pipe (15), and one end of the water outlet pipe (15) away from the cavity (10) is used to be connected to a steam-water separator.

7. The nuclear steam supply system according to claim 1, characterized in that: The cross-sectional shape of the first pipe (4) and the cross-sectional shape of the second pipe (5) are mirror images of each other, and the cross-sectional shape of the first pipe (4) is semi-elliptical.

8. The nuclear steam supply system according to claim 7, characterized in that: The cross section of the first pipe (4) comprises a first straight line segment and a first elliptical arc segment connected end to end with the first straight line segment, and the first straight line segment extends along the major axis direction of the first elliptical arc segment.

9. The nuclear steam supply system according to claim 8, characterized in that: The first pipes (4) and the second pipes (5) are arranged in a plurality of rows at equal distances along the extension direction of the first straight line segment; The first pipes (4) arranged in a row and the second pipes (5) arranged in a row are alternately arranged along a first direction; The first direction is perpendicular to the extension direction of the first straight line segment, and both are perpendicular to the extension direction of the first pipe (4).

10. The nuclear steam supply system according to claim 8, characterized in that: The cross section of the second pipe (5) comprises a second straight line segment and a second elliptical arc segment connected end to end with the second straight line segment; The second straight line segment is parallel to the first straight line segment, and the bulging direction of the semi-elliptical cross section of the first pipe (4) is opposite to the bulging direction of the semi-elliptical cross section of the second pipe (5).

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