CN219264243U - Split type direct current steam generator suitable for high temperature gas cooled reactor nuclear power unit - Google Patents
Split type direct current steam generator suitable for high temperature gas cooled reactor nuclear power unit Download PDFInfo
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- CN219264243U CN219264243U CN202320172892.8U CN202320172892U CN219264243U CN 219264243 U CN219264243 U CN 219264243U CN 202320172892 U CN202320172892 U CN 202320172892U CN 219264243 U CN219264243 U CN 219264243U
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- superheater
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The utility model discloses a split type direct current steam generator suitable for a high-temperature gas cooled reactor nuclear power unit, which comprises an evaporator body and a superheater body; the heat release side of the evaporator body is connected with the heat release side of the superheater body through the medium-temperature helium gas communicating pipe inner pipe and the medium-temperature helium gas communicating pipe outer pipe, the heat release side of the superheater body is connected with the reactor through the high-temperature helium gas communicating pipe outer pipe and the high-temperature helium gas communicating pipe inner pipe, the heat absorption side of the evaporator body is communicated with the heat absorption side of the superheater body, and the steam generator can avoid the problem caused by overlong heat transfer pipes.
Description
Technical Field
The utility model belongs to the technical field of reactor nuclear motor group steam generators, and relates to a split type direct current steam generator suitable for a high-temperature gas cooled reactor nuclear power unit.
Background
The high-temperature gas cooled reactor nuclear power unit steam generator adopts a spiral tube type steam generator, and because helium gas has low heat density and needs a very large heat exchange area, the volume of the steam generator adopted at present is very large, and the difficulty of equipment manufacturing, transportation and hoisting is improved. Meanwhile, the heat transfer tube of the current steam generator is spliced by two metal materials, namely, the evaporation section is made of T22, the superheating section is made of Incoloy 800H materials, adverse effects can be generated on the welding seam of the T22 and the Incoloy 800H due to factors such as flow vibration, graphite dust carburization and thermal stress during unit operation, and the heat transfer tube is far longer than that of a conventional pressurized water reactor steam generator, so that the periodic flaw detection, analysis and overhaul of the heat transfer tube are restricted to different degrees.
Disclosure of Invention
The utility model aims to overcome the defects of the prior art and provides a split type direct current steam generator suitable for a high-temperature gas cooled reactor nuclear power unit, which can avoid the problem caused by overlong heat transfer tubes.
In order to achieve the purpose, the split type direct current steam generator suitable for the high-temperature gas cooled reactor nuclear power unit comprises an evaporator body and a superheater body;
the heat release side of the evaporator body is connected with the heat release side of the superheater body through a medium-temperature helium gas communicating pipe inner pipe and a medium-temperature helium gas communicating pipe outer pipe, the heat release side of the superheater body is connected with the reactor through a high-temperature helium gas communicating pipe outer pipe and a high-temperature helium gas communicating pipe inner pipe, and the heat absorption side of the evaporator body is communicated with the heat absorption side of the superheater body.
An evaporator heat exchange assembly is arranged in the evaporator body; the superheater body is internally provided with a superheater heat exchange assembly, and the shape of a heat transfer pipe in the evaporator heat exchange assembly and the superheater heat exchange assembly is a spiral pipe, a straight pipe or an S-shaped pipe.
The evaporator heat exchange assembly is sleeved with an evaporator heat insulation layer, the interior of the evaporator body is divided into a shell side area of the evaporator heat exchange assembly and an evaporator Leng Haiqi flow passage positioned between the evaporator body and the evaporator heat insulation layer by the evaporator heat insulation layer, a plurality of helium guide holes are formed in the side face of the bottom of the evaporator heat insulation layer, and the shell side area of the evaporator heat exchange assembly is communicated with the evaporator cold helium flow passage through the helium guide holes;
the outer part of the superheater heat exchange assembly is sleeved with a superheater heat insulation layer, and the interior of the superheater body is divided into a shell side region of the superheater heat exchange assembly and a superheater Leng Haiqi runner between the superheater heat insulation layer and the inner wall of the superheater body by the superheater heat insulation layer;
the bottom outlet of the shell side area of the superheater heat exchange assembly is communicated with the top inlet of the shell side area of the evaporator heat exchange assembly through an inner tube of the medium-temperature helium communicating tube, the bottom of the shell side area of the evaporator heat exchange assembly is communicated with the bottom of the evaporator cold helium flow passage through a helium guide hole, and the top outlet of the evaporator cold helium flow passage is communicated with the bottom inlet of the superheater cold helium flow passage through an outer tube of the medium-temperature helium communicating tube.
The helium guide holes are round holes, and each helium guide hole is circumferentially arranged.
The device also comprises a cold helium collecting pipe and a main helium blower; the top outlet of the superheater cold helium flow channel is communicated with the inlet of the main helium fan through a cold helium collecting pipe, the outlet of the main helium fan is communicated with the inlet of the reactor through a high-temperature helium communicating pipe outer pipe, the outlet of the reactor is communicated with the top inlet of the shell side area of the superheater heat exchange assembly through a high-temperature helium communicating pipe inner pipe, and the high-temperature helium communicating pipe inner pipe is sleeved in the high-temperature helium communicating pipe outer pipe.
The water supply header and the steam header are also included;
the top of the superheater body is provided with a superheater upper end socket, the bottom of the superheater body is provided with a superheater lower end socket, and the superheater lower end socket is provided with a superheater lower end socket communicating pipe interface;
the top of the evaporator body is provided with an evaporator upper end socket, the bottom of the evaporator body is provided with an evaporator lower end socket, and the evaporator upper end socket is provided with an evaporator upper end socket communicating pipe interface;
the outlet of the water supply header is communicated with the inlet of the heat transfer tube of the evaporator heat exchange assembly through the water supply distributing tube, the outlet of the heat transfer tube of the evaporator heat exchange assembly is communicated with the upper end socket of the evaporator, the interface of the upper end socket communicating tube of the evaporator is communicated with the interface of the lower end socket communicating tube of the superheater through the steam communicating tube, a flow distributing pore plate is arranged in the lower end socket of the superheater, the lower end socket of the superheater is communicated with the inlet of the heat transfer tube of the superheater heat exchange assembly through a distributing hole on the flow distributing pore plate, and the outlet of the heat transfer tube of the superheater heat exchange assembly is communicated with the steam header through the steam collecting tube.
And a manhole of the upper sealing head of the superheater is arranged on the upper sealing head of the superheater.
And a manhole of the lower sealing head of the superheater is arranged on the lower sealing head of the superheater.
The evaporator lower end socket is provided with an evaporator lower end socket manhole.
The upper end socket of the evaporator is provided with an interface of a communicating pipe of the upper end socket of the evaporator.
The utility model has the following beneficial effects:
the split type direct current steam generator suitable for the high-temperature gas cooled reactor nuclear power unit adopts a split type structure to shorten the length of the heat transfer pipe and avoid various problems caused by overlong heat transfer pipes, and particularly, the heat release side of the evaporator body is connected with the heat release side of the superheater body through the inner pipe of the medium-temperature helium communicating pipe and the outer pipe of the medium-temperature helium communicating pipe, the heat absorption side of the evaporator body is communicated with the heat absorption side of the superheater body, the volume of single equipment is obviously reduced, the difficulty of equipment manufacturing, transportation and hoisting is reduced, and the periodic flaw detection, analysis and overhaul of the heat transfer pipe are facilitated.
Drawings
FIG. 1 is a block diagram of the present utility model;
fig. 2 is a top view of the present utility model.
The evaporator comprises an evaporator body 1, an evaporator lower head manhole 3, an evaporator lower head manhole 4, a water supply header 4, a water supply distributing pipe 4-1, a helium guide hole 5, an evaporator heat exchange component 6, an evaporator heat insulation layer 7, an evaporator Leng Haiqi runner 8, an evaporator upper head 9, an evaporator upper head manhole 10, an evaporator upper head communicating pipe interface 11, a steam communicating pipe 12, a medium-temperature helium communicating pipe inner pipe 13, a medium-temperature helium communicating pipe outer pipe 14, a superheater body 15, a superheater lower head 16, a superheater lower head communicating pipe interface 17, a superheater lower head manhole 18, a flow distribution orifice 19, a superheater heat exchange component 20, a superheater heat exchange component 21, a superheater Leng Haiqi runner 22, a cold helium collecting pipe 23, a superheater upper head 24, a main helium fan 25, a superheater upper head manhole 26, a high-temperature helium outer pipe 27, a high-temperature communicating pipe inner pipe 28, a steam collecting pipe 29, a steam header 30 and a reactor 31.
Detailed Description
In order to make the present utility model better understood by those skilled in the art, the following description will clearly and completely describe the technical solutions in the embodiments of the present utility model with reference to the accompanying drawings, and it is apparent that the described embodiments are only some embodiments of the present utility model, not all embodiments, but not intended to limit the scope of the present disclosure. In addition, in the following description, descriptions of well-known structures and techniques are omitted so as not to unnecessarily obscure the concepts of the present disclosure. All other embodiments, which can be made by those skilled in the art based on the embodiments of the present utility model without making any inventive effort, shall fall within the scope of the present utility model.
In the accompanying drawings, there is shown a schematic structural diagram in accordance with a disclosed embodiment of the utility model. The figures are not drawn to scale, wherein certain details are exaggerated for clarity of presentation and may have been omitted. The shapes of the various regions, layers and their relative sizes, positional relationships shown in the drawings are merely exemplary, may in practice deviate due to manufacturing tolerances or technical limitations, and one skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions as actually required.
Referring to fig. 1 and 2, the split type direct current steam generator suitable for a high temperature gas cooled reactor nuclear power unit according to the present utility model comprises an evaporator body 1 and a superheater body 15;
the evaporator body 1 is connected with the superheater body 15 through the medium-temperature helium gas communicating pipe inner pipe 13 and the medium-temperature helium gas communicating pipe outer pipe 14, the position of the evaporator body 1 is lower than that of the superheater body 15, and the superheater body 15 is connected with the reactor 31 through the high-temperature helium gas communicating pipe outer pipe 27 and the high-temperature helium gas communicating pipe inner pipe 28.
The heat transfer tube material of the evaporator heat exchange assembly 6 in the evaporator body 1 is T22, and the heat transfer tube material of the superheater heat exchange assembly 20 in the superheater body 15 is Incoloy 800H.
The heat transfer tubes in the evaporator heat exchange assembly 6 and the superheater heat exchange assembly 20 are in the shape of spiral tubes, straight tubes or S-shaped tubes.
The evaporator heat exchange assembly 6 is sleeved with an evaporator heat insulation layer 7, and helium inside the evaporator body 1 is isolated into two relatively independent flowing areas through the evaporator heat insulation layer 7, namely a shell side area of the evaporator heat exchange assembly 6 and an evaporator cold helium flow channel 8 positioned between the evaporator body 1 and the evaporator heat insulation layer 7.
It should be noted that, be provided with a plurality of helium guide holes 5 on the side of evaporator insulating layer 7 bottom, the shell side region of evaporator heat transfer module 6 and the cold helium runner 8 of evaporator are through helium guide holes 5 intercommunication, and helium guide holes 5 are round hole form, and each helium guide hole 5 is arranged along circumference, has flow distribution function simultaneously.
The outer part of the superheater heat exchange assembly 20 is sleeved with a superheater heat insulation layer 21, and helium in the superheater body 15 is isolated into two relatively independent flow areas through the superheater heat insulation layer 21, namely a shell side area of the superheater heat exchange assembly 20 and a superheater cold helium flow passage 22 between the superheater heat insulation layer 21 and the inner wall of the superheater body 15;
the bottom outlet of the shell side area of the superheater heat exchange assembly 20 is communicated with the top inlet of the shell side area of the evaporator heat exchange assembly 6 through a medium-temperature helium gas communicating pipe inner pipe 13, the bottom of the shell side area of the evaporator heat exchange assembly 6 is communicated with the bottom of the evaporator cold helium gas flow passage 8 through a helium gas guide hole 5, and the top outlet of the evaporator cold helium gas flow passage 8 is communicated with the bottom inlet of the superheater cold helium gas flow passage 22 through a medium-temperature helium gas communicating pipe outer pipe 14.
The top outlet of the superheater cold helium flow passage 22 is communicated with the inlet of the main helium fan 25 through a cold helium collecting pipe 23, the outlet of the main helium fan 25 is communicated with the inlet of the reactor 31 through a high-temperature helium communicating pipe outer pipe 27, the outlet of the reactor 31 is communicated with the top inlet of the shell side area of the superheater heat exchange assembly 20 through a high-temperature helium communicating pipe inner pipe 28, and the high-temperature helium communicating pipe inner pipe 28 is sleeved in the high-temperature helium communicating pipe outer pipe 27.
The top of the superheater body 15 is provided with a superheater upper end socket 24, the bottom of the superheater body 15 is provided with a superheater lower end socket 16, and the superheater upper end socket 24 is provided with a superheater upper end socket manhole 26; the superheater lower end socket 16 is provided with a superheater lower end socket communicating pipe interface 17 and a superheater lower end socket manhole 18;
the top of the evaporator body 1 is provided with an evaporator upper end socket 9, the bottom of the evaporator body 1 is provided with an evaporator lower end socket 2, and the evaporator upper end socket 9 is provided with an evaporator upper end socket manhole 10 and an evaporator upper end socket communicating pipe joint 11; the evaporator lower end enclosure 2 is provided with an evaporator lower end enclosure manhole 3;
the outlet of the water supply header 4 is communicated with the inlet of the heat transfer tube of the evaporator heat exchange assembly 6 through the water supply distribution tube 4-1, the outlet of the heat transfer tube of the evaporator heat exchange assembly 6 is communicated with the upper end socket 9 of the evaporator, the upper end socket communicating tube interface 11 of the evaporator is communicated with the lower end socket communicating tube interface 17 of the superheater through the steam communicating tube 12, the flow distribution pore plate 19 is arranged in the lower end socket 16 of the superheater, the lower end socket 16 of the superheater is communicated with the inlet of the heat transfer tube of the superheater heat exchange assembly 20 through the distribution pore plate 19, and the outlet of the heat transfer tube of the superheater heat exchange assembly 20 is communicated with the steam header 30 through the steam collecting tube 29.
The main helium fan 25 is arranged on the upper end enclosure 24 of the superheater, a transmission shaft between a motor of the main helium fan 25 and the fan passes through a manhole 26 of the upper end enclosure of the superheater, and the transmission shaft of the main helium fan 25 has a corresponding sealing and cooling structure.
The specific working process of the utility model is as follows:
steam-water measurement: the feed water is supplied from a feed water header 4 in the evaporator lower head 2 to a heat transfer tube in the evaporator heat exchange assembly 6 through a feed water distributing tube 4-1, flows upwards at the tube side of the evaporator heat exchange assembly 6, exchanges heat with medium-temperature helium gas flowing downwards in the shell side of the evaporator heat exchange assembly 6 to become slightly superheated steam, is mixed in the evaporator upper head 9, then enters a chamber in which the superheater lower head 16 is positioned through a steam communicating tube 12, is subjected to flow distribution through a flow distribution orifice 19, then continues to flow upwards at the tube side of the superheater heat exchange assembly 20, and further exchanges heat with high-temperature helium gas to rise temperature, and finally enters a steam header 30 through a steam collecting tube 29.
Helium side: the high-temperature helium flows out of the reactor core of the reactor 31, flows downwards through the high-temperature helium communicating pipe inner pipe 28 into the superheater body 15, flows downwards through the shell side of the superheater heat exchange assembly 20, becomes medium-temperature helium after cooling, flows through the medium-temperature helium communicating pipe inner pipe 13 into the shell side of the evaporator heat exchange assembly 6, flows downwards through the shell side of the evaporator heat exchange assembly 6, further exchanges heat and cools to become low-temperature helium after cooling, flows upwards along the evaporator cold helium flow channel 8 between the evaporator heat exchange assembly 6 and the inner wall of the evaporator body 1, flows into the superheater through the annular channel between the medium-temperature helium communicating pipe inner pipe 13 and the medium-temperature helium communicating pipe outer pipe 14, continuously flows upwards through the superheater cold helium flow channel 22 between the superheater body 15 and the superheater heat exchange assembly 21, finally flows into the chamber of the main helium fan 25 through the helium collecting pipe 23, flows downwards through the shell side of the main helium fan 25 after being pressurized, flows into the annular flow channel between the high-temperature communicating pipe 28 and the high-temperature helium communicating pipe outer pipe 27, finally flows into the reactor 31, and then flows into the next circulation system 。
Finally, it should be noted that: the above embodiments are only for illustrating the technical aspects of the present utility model and not for limiting the same, and although the present utility model has been described in detail with reference to the above embodiments, it should be understood by those of ordinary skill in the art that: modifications and equivalents may be made to the specific embodiments of the utility model without departing from the spirit and scope of the utility model, which is intended to be covered by the claims.
Claims (10)
1. The split type direct current steam generator suitable for the high-temperature gas cooled reactor nuclear power unit is characterized by comprising an evaporator body (1) and a superheater body (15);
the heat release side of the evaporator body (1) is connected with the heat release side of the superheater body (15) through a medium-temperature helium gas communicating pipe inner pipe (13) and a medium-temperature helium gas communicating pipe outer pipe (14), the heat release side of the superheater body (15) is connected with the reactor (31) through a high-temperature helium gas communicating pipe outer pipe (27) and a high-temperature helium gas communicating pipe inner pipe (28), and the heat absorption side of the evaporator body (1) is communicated with the heat absorption side of the superheater body (15).
2. The split type once-through steam generator suitable for a high-temperature gas cooled reactor nuclear power unit according to claim 1, wherein an evaporator heat exchange assembly (6) is arranged in the evaporator body (1); the superheater body (15) is internally provided with a superheater heat exchange assembly (20), and the evaporator heat exchange assembly (6) and heat transfer pipes in the superheater heat exchange assembly (20) are spiral pipes, straight pipes or S-shaped pipes.
3. The split type once-through steam generator suitable for a high-temperature gas cooled reactor nuclear power unit according to claim 1, wherein an evaporator heat exchange assembly (6) is sleeved with an evaporator heat insulation layer (7), the evaporator heat insulation layer (7) divides the interior of the evaporator body (1) into a shell side area of the evaporator heat exchange assembly (6) and an evaporator Leng Haiqi runner (8) positioned between the evaporator body (1) and the evaporator heat insulation layer (7), a plurality of helium guide holes (5) are formed in the side surface of the bottom of the evaporator heat exchange assembly (7), and the shell side area of the evaporator heat exchange assembly (6) is communicated with the evaporator Leng Haiqi runner (8) through the helium guide holes (5);
the outer part of the superheater heat exchange assembly (20) is sleeved with a superheater heat insulation layer (21), and the interior of the superheater body (15) is divided into a shell side area of the superheater heat exchange assembly (20) and a superheater Leng Haiqi runner (22) between the superheater heat insulation layer (21) and the inner wall of the superheater body (15) by the superheater heat insulation layer (21);
the bottom outlet of the shell side area of the superheater heat exchange assembly (20) is communicated with the top inlet of the shell side area of the evaporator heat exchange assembly (6) through a medium-temperature helium gas communicating pipe inner pipe (13), the bottom of the shell side area of the evaporator heat exchange assembly (6) is communicated with the bottom of the evaporator Leng Haiqi runner (8) through a helium gas guide hole (5), and the top outlet of the evaporator Leng Haiqi runner (8) is communicated with the bottom inlet of the superheater Leng Haiqi runner (22) through a medium-temperature helium gas communicating pipe outer pipe (14).
4. A split type direct current steam generator suitable for a high temperature gas cooled reactor nuclear power unit according to claim 3, wherein the helium gas guide holes (5) are circular holes, and each helium gas guide hole (5) is circumferentially arranged.
5. A split dc steam generator suitable for use in a high temperature gas cooled reactor nuclear power unit according to claim 3, further comprising a cold helium manifold (23) and a primary helium fan (25); the top outlet of the superheater Leng Haiqi runner (22) is communicated with the inlet of the main helium fan (25) through a cold helium collecting pipe (23), the outlet of the main helium fan (25) is communicated with the inlet of the reactor (31) through a high-temperature helium communicating pipe outer pipe (27), the outlet of the reactor (31) is communicated with the top inlet of the shell side area of the superheater heat exchange assembly (20) through a high-temperature helium communicating pipe inner pipe (28), and the high-temperature helium communicating pipe inner pipe (28) is sleeved in the high-temperature helium communicating pipe outer pipe (27).
6. A split once-through steam generator suitable for use in a high temperature gas cooled reactor nuclear power unit as claimed in claim 3, further comprising a water feed header (4) and a steam header (30);
the top of the superheater body (15) is provided with a superheater upper end socket (24), the bottom of the superheater body (15) is provided with a superheater lower end socket (16), and the superheater lower end socket (16) is provided with a superheater lower end socket communicating pipe interface (17);
the top of the evaporator body (1) is provided with an evaporator upper end socket (9), the bottom of the evaporator body (1) is provided with an evaporator lower end socket (2), and the evaporator upper end socket (9) is provided with an evaporator upper end socket communicating pipe interface (11);
the outlet of the water supply header (4) is communicated with the inlet of the heat transfer tube of the evaporator heat exchange assembly (6) through the water supply distributing tube (4-1), the outlet of the heat transfer tube of the evaporator heat exchange assembly (6) is communicated with the upper end socket (9) of the evaporator, the upper end socket communicating tube interface (11) of the evaporator is communicated with the lower end socket communicating tube interface (17) of the superheater through the steam communicating tube (12), the flow distributing hole plate (19) is arranged in the lower end socket (16) of the superheater, the lower end socket (16) of the superheater is communicated with the inlet of the heat transfer tube of the superheater heat exchange assembly (20) through the distributing hole on the flow distributing hole plate (19), and the outlet of the heat transfer tube of the superheater heat exchange assembly (20) is communicated with the steam header (30) through the steam collecting tube (29).
7. The split type direct current steam generator suitable for a high temperature gas cooled reactor nuclear power unit as recited in claim 6, wherein a superheater upper head manhole (26) is arranged on the superheater upper head (24).
8. The split type direct current steam generator suitable for a high temperature gas cooled reactor nuclear power unit as claimed in claim 6, wherein a superheater lower head manhole (18) is arranged on the superheater lower head (16).
9. The split type direct current steam generator suitable for the high-temperature gas cooled reactor nuclear power unit according to claim 6, wherein an evaporator lower end socket manhole (3) is arranged on the evaporator lower end socket (2).
10. The split type direct current steam generator suitable for the high temperature gas cooled reactor nuclear power unit according to claim 6, wherein an evaporator upper end socket (9) is provided with an evaporator upper end socket communicating pipe joint (11).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320172892.8U CN219264243U (en) | 2023-02-09 | 2023-02-09 | Split type direct current steam generator suitable for high temperature gas cooled reactor nuclear power unit |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320172892.8U CN219264243U (en) | 2023-02-09 | 2023-02-09 | Split type direct current steam generator suitable for high temperature gas cooled reactor nuclear power unit |
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| Publication Number | Publication Date |
|---|---|
| CN219264243U true CN219264243U (en) | 2023-06-27 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202320172892.8U Active CN219264243U (en) | 2023-02-09 | 2023-02-09 | Split type direct current steam generator suitable for high temperature gas cooled reactor nuclear power unit |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN219264243U (en) |
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2023
- 2023-02-09 CN CN202320172892.8U patent/CN219264243U/en active Active
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