CN113719817A - High-temperature gas cooled reactor steam generator with blowdown function - Google Patents
High-temperature gas cooled reactor steam generator with blowdown function Download PDFInfo
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- CN113719817A CN113719817A CN202110991386.7A CN202110991386A CN113719817A CN 113719817 A CN113719817 A CN 113719817A CN 202110991386 A CN202110991386 A CN 202110991386A CN 113719817 A CN113719817 A CN 113719817A
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- flow channel
- steam
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- 239000001307 helium Substances 0.000 claims abstract description 39
- 229910052734 helium Inorganic materials 0.000 claims abstract description 39
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims abstract description 39
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 34
- 239000007789 gas Substances 0.000 claims abstract description 27
- 230000001174 ascending effect Effects 0.000 claims abstract description 9
- 238000009826 distribution Methods 0.000 claims abstract description 9
- 238000005192 partition Methods 0.000 claims description 6
- 230000000712 assembly Effects 0.000 claims description 3
- 238000000429 assembly Methods 0.000 claims description 3
- 238000007789 sealing Methods 0.000 claims 3
- 230000007306 turnover Effects 0.000 claims 3
- 239000000758 substrate Substances 0.000 abstract description 3
- 238000012546 transfer Methods 0.000 description 24
- 239000011159 matrix material Substances 0.000 description 8
- 238000012423 maintenance Methods 0.000 description 5
- 238000007689 inspection Methods 0.000 description 4
- 238000001816 cooling Methods 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- 238000004140 cleaning Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 239000000428 dust Substances 0.000 description 2
- 229910002804 graphite Inorganic materials 0.000 description 2
- 239000010439 graphite Substances 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000008646 thermal stress Effects 0.000 description 2
- 230000005856 abnormality Effects 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000011418 maintenance treatment Methods 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 239000013049 sediment Substances 0.000 description 1
Images
Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B31/00—Modifications of boiler construction, or of tube systems, dependent on installation of combustion apparatus; Arrangements of dispositions of combustion apparatus
- F22B31/08—Installation of heat-exchange apparatus or of means in boilers for heating air supplied for combustion
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/22—Drums; Headers; Accessories therefor
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/38—Determining or indicating operating conditions in steam boilers, e.g. monitoring direction or rate of water flow through water tubes
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/48—Devices for removing water, salt, or sludge from boilers; Arrangements of cleaning apparatus in boilers; Combinations thereof with boilers
- F22B37/54—De-sludging or blow-down devices
- F22B37/545—Valves specially adapted therefor
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/56—Boiler cleaning control devices, e.g. for ascertaining proper duration of boiler blow-down
- F22B37/565—Blow-down control, e.g. for ascertaining proper duration of boiler blow-down
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
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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
Abstract
The invention discloses a high-temperature gas cooled reactor steam generator with a blowdown function, which comprises a steam generator substrate, a main water supply system, a main steam system, a steam generator continuous blowdown system and a steam generator accident discharge system, wherein the steam generator substrate is provided with a water inlet pipe and a water outlet pipe; a steam generator upper end enclosure is arranged at the opening at the top of the steam generator base body, a steam generator lower end enclosure is arranged at the opening at the bottom of the steam generator base body, and a steam generator bottom helium chamber is formed in the steam generator lower end enclosure; the outlet of the hot helium distribution chamber is communicated with the cold helium outlet chamber through a loop medium heat exchange flow channel, a steam generator lower end enclosure and a helium gas ascending flow channel; the two-loop medium heat exchange flow channel is communicated with a steam generator continuous blowdown system through a steam generator continuous blowdown valve, the two-loop medium heat exchange flow channel is communicated with the steam generator accident discharge system through a steam generator accident discharge valve group, and the generator has blowdown capability, high safety and low scaling risk.
Description
Technical Field
The invention belongs to the field of nuclear energy development and utilization, and relates to a high-temperature gas cooled reactor steam generator with a pollution discharge function.
Background
A primary loop device of a high-temperature gas cooled reactor in the field of nuclear energy development mainly comprises four parts, namely a reactor, a hot gas guide pipe, a helium main fan, a steam generator and the like, wherein a spiral pipe of a vertical type and direct-current spiral pipe type steam generator designed at present cannot pass eddy current detection, cannot be inspected in service, and cannot find abnormality of a heat transfer pipe in time under the condition of shutdown so as to take measures in advance; when the heat transfer pipe is broken, the high-energy pipeline has a whipping effect, so that the accident is expanded, and in addition, when the steam generator is discharged in an accident, the steam of the secondary loop can be discharged from a single discharge flow channel, so that the discharge efficiency is low, and the risk of water inflow of the primary loop is high; when the heat transfer pipe needs to be blocked or subjected to other maintenance treatment, the maintenance is extremely difficult; under the normal operation condition, the temperature of superheated steam from the inlet of a secondary loop of the steam generator to the outlet of subcooled water changes from 200 ℃ to 600 ℃, the metal of the heat transfer pipe has large thermal stress, and the heat transfer pipe has large processing and manufacturing difficulty; the two-loop water vapor directly passes through the steam generator without pollution discharge capacity, so that concentrated impurities in the heat transfer pipe bundle are increased, and the problems of heat transfer efficiency reduction, sediment corrosion and the like exist.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a high-temperature gas cooled reactor steam generator with a pollution discharge function, which has the advantages of pollution discharge capability, high safety and low scaling risk.
In order to achieve the aim, the high-temperature gas cooled reactor steam generator with the blowdown function comprises a steam generator base body, a main water supply system, a main steam system, a steam generator continuous blowdown system and a steam generator accident discharge system;
a steam generator upper end enclosure is arranged at the opening at the top of the steam generator base body, a steam generator lower end enclosure is arranged at the opening at the bottom of the steam generator base body, and a steam generator bottom helium chamber is formed in the steam generator lower end enclosure;
a secondary loop medium heat exchange flow channel is arranged in the steam generator base body, and a primary loop medium heat exchange flow channel is formed between the secondary loop medium heat exchange flow channel and the steam generator base body;
the outlet of the main water supply system is communicated with the inlet of the two-loop medium heat exchange flow passage, and the outlet of the two-loop medium heat exchange flow passage is communicated with the main steam system;
the upper end enclosure of the steam generator is a cold helium outlet chamber and a hot helium distribution chamber through an inner shell partition plate of the upper end enclosure, helium gas ascending flow channels are arranged on two sides of a base body of the steam generator, and an outlet of the hot helium distribution chamber is communicated with the cold helium outlet chamber through a loop medium heat exchange flow channel, a lower end enclosure of the steam generator and the helium gas ascending flow channels;
the two-loop medium heat exchange flow channel is communicated with a continuous blowdown system of the steam generator through a continuous blowdown valve of the steam generator, and the two-loop medium heat exchange flow channel is communicated with an accident discharge system of the steam generator through an accident discharge valve group of the steam generator.
A main water supply inlet chamber is arranged on the side surface of the steam generator base body; the outlet of the main water supply system is communicated with the inlet of the two-loop medium heat exchange flow passage through the main water supply inlet chamber.
A main steam outlet chamber is arranged on the side surface of the steam generator base body; the outlet of the two-loop medium heat exchange flow channel is communicated with the main steam system through the main steam outlet chamber.
The two-loop medium heat exchange flow channel comprises a first-stage heat exchange assembly, a second-stage heat exchange assembly, a third-stage heat exchange assembly, a fourth-stage heat exchange assembly, a fifth-stage heat exchange assembly, a sixth-stage heat exchange assembly and a seventh-stage heat exchange assembly which are sequentially communicated, and adjacent two-stage heat exchange assemblies are communicated through a steering seal head;
the upper end enclosure, the inner shell partition plate of the upper end enclosure and the lower end enclosure of the steam generator are all detachable structures.
Each turning seal head is communicated with a continuous blowdown system of the steam generator through a continuous blowdown valve of the steam generator.
Each steering seal head is communicated with the steam generator accident discharge system through a steam generator accident discharge valve group;
each steering seal head is a detachable device.
The invention has the following beneficial effects:
when the high-temperature gas cooled reactor steam generator with the blowdown function is in specific operation, after a primary loop detects a humidity signal, the primary loop and the secondary loop are broken, and the steam generator accident discharge valve group is automatically opened. When the unit is started, in order to quickly heat the heat transfer matrix or reversely heat the primary loop, the continuous blowdown valve group of the steam generator is opened, and two loops of high-temperature water or steam are introduced from the main water supply or main steam system for heating; in order to quickly cool the heat transfer matrix and reduce the helium temperature of a primary loop at the initial shutdown stage of the unit, low-temperature water can be introduced from a main water supply system for cooling by opening a continuous blowdown valve group of a steam generator, and the invention needs to be explained by canceling a heat transfer tube bundle structure, avoiding the problem of high-energy pipeline whipping caused by the broken opening of the heat transfer tube bundle and avoiding the problem of thermal stress caused by large temperature rise of a medium of a secondary loop; the problem that two loops of each heat transfer flow channel are communicated is avoided. In addition, a steam generator accident discharge valve group is arranged on the steering seal head to increase the discharge capacity of two loops of media, and the safety performance is improved by the multiple redundant steam generator accident discharge valve groups; a steam generator continuous blowdown valve is additionally arranged on the accident discharge pipeline, continuous blowdown is carried out in the two-loop water vapor evaporation process, the scaling risk is reduced, and the steam generator continuous blowdown valve can also have the functions of preheating starting and cooling stopping of the two loops; after a certain stage of heat exchange assembly is blocked, the influence on the whole heat exchange efficiency and the through-flow capacity of the steam generator is small.
Furthermore, the upper end socket and the lower end socket of the steam generator are of detachable structures, and after the upper end socket and the lower end socket are detached during shutdown maintenance, in-service inspection of a loop heat transfer tube bundle can be performed, deposits such as graphite dust in the heat transfer tube bundle are cleaned, and heat transfer efficiency is guaranteed not to be reduced.
Furthermore, each steering seal head is a detachable device, and after the device is detached, in-service inspection, pipe plugging, cleaning and maintenance of the two-loop heat transfer flow channel can be carried out. When the condition that the first loop and the second loop are leaked is blocked in a certain level, the influence on the through flow and the heat exchange efficiency of the heat exchange assembly of the level is only generated, and the influence on the overall through flow and the heat exchange of the steam generator is small.
Drawings
FIG. 1 is a schematic structural view of the present invention;
FIG. 2 is an axial cross-sectional top view of the present invention;
FIG. 3 is a front view in radial cross-section of the present invention;
fig. 4 is a top plan view of the present invention.
Wherein, 1 is a steam generator substrate, 2-1 is a main water supply system, 2-2 is a main steam system, 3 is a steam generator accident discharge system, 4 is hot helium, 5 is cold helium, 6 is a cold helium outlet chamber, 7 is a hot helium distribution chamber, 8 is a steam generator lower head, 9 is a steam generator bottom helium chamber, 10-1 is a steam generator upper head, 10-2 is an upper head inner shell clapboard, 11 is a main steam outlet chamber, 12 is a main water supply inlet chamber, 13 is a steering head, 14 is a two-loop medium heat exchange flow channel, 15 is a primary loop medium heat exchange flow channel, 16 is a helium ascending flow channel, 17-1 is a first-stage heat exchange component, 17-2 is a second-stage heat exchange component, 17-3 is a third-stage heat exchange component, 17-4 is a fourth-stage heat exchange component, 17-5 is a fifth-stage heat exchange component, 17-6 is a sixth-stage heat exchange assembly, 17-7 is a seventh-stage heat exchange assembly, 18 is a steam generator accident discharge valve group, 19 is a steam generator continuous blowdown valve, and 20 is a steam generator continuous blowdown system.
Detailed Description
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, not all of the embodiments, and are not intended to limit the scope of the present disclosure. Moreover, in the following description, descriptions of well-known structures and techniques are omitted so as to not unnecessarily obscure the concepts of the present disclosure. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
There is shown in the drawings a schematic block diagram of a disclosed embodiment in accordance with the invention. The figures are not drawn to scale, wherein certain details are exaggerated and possibly omitted for clarity of presentation. The shapes of various regions, layers and their relative sizes and positional relationships shown in the drawings are merely exemplary, and deviations may occur in practice due to manufacturing tolerances or technical limitations, and a person skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions, according to actual needs.
Referring to fig. 1, 2, 3 and 4, the steam generator of the high temperature gas cooled reactor with a blowdown function according to the present invention includes a steam generator base 1, a main water supply system 2-1, a main steam system 2-2, a steam generator continuous blowdown system 20 and a steam generator emergency blowdown system 3;
a steam generator upper end enclosure 10-1 is arranged at the opening at the top of the steam generator base body 1, a steam generator lower end enclosure 8 is arranged at the opening at the bottom of the steam generator base body 1, and a steam generator bottom helium chamber 9 is formed in the steam generator lower end enclosure 8;
the side surface of the steam generator matrix 1 is provided with a main feed water inlet chamber 12 and a main steam outlet chamber 11;
a secondary loop medium heat exchange flow channel 14 is arranged in the steam generator base body 1, and a primary loop medium heat exchange flow channel 15 is formed between the secondary loop medium heat exchange flow channel 14 and the steam generator base body 1;
the outlet of the main water supply system 2-1 is communicated with the inlet of a secondary loop medium heat exchange flow passage 14 through a main water supply inlet chamber 12, and the outlet of the secondary loop medium heat exchange flow passage 14 is communicated with the main steam system 2-2 through a main steam outlet chamber 11;
the secondary loop medium heat exchange flow channel 14 comprises a first-stage heat exchange assembly 17-1, a second-stage heat exchange assembly 17-2, a third-stage heat exchange assembly 17-3, a fourth-stage heat exchange assembly 17-4, a fifth-stage heat exchange assembly 17-5, a sixth-stage heat exchange assembly 17-6 and a seventh-stage heat exchange assembly 17-7 which are communicated in sequence, and adjacent two stages of heat exchange assemblies are communicated through a steering seal head 13;
an upper end enclosure 10-1 of the steam generator is divided into a cold helium outlet chamber 6 and a hot helium distribution chamber 7 by an inner shell partition plate 10-2 of the upper end enclosure, helium gas ascending flow channels 16 are arranged on two sides of a base body 1 of the steam generator, and an outlet of the hot helium distribution chamber 7 is communicated with the cold helium outlet chamber 6 through a loop medium heat exchange flow channel 15, a lower end enclosure 8 of the steam generator and the helium gas ascending flow channels 16;
the steam generator matrix 1 is a main part for the first loop and the second loop heat transfer, a loop hot helium gas 4 enters a hot helium distribution chamber 7, then flows through a loop medium heat exchange flow channel 15 from top to bottom, transfers heat to a secondary loop steam water in a secondary loop medium heat exchange flow channel 14 through the steam generator matrix 1, the helium gas after heat exchange is collected in a steam generator lower end enclosure 8, then flows into a steam generator upper end enclosure 10-1 from helium gas ascending flow channels 16 at two sides of the steam generator matrix 1, and then flows out of the steam generator from a cold helium outlet chamber 6.
The upper end enclosure 10-1 of the steam generator, the inner shell partition plate 10-2 of the upper end enclosure and the lower end enclosure 8 of the steam generator are all detachable structures, and after detachment during shutdown maintenance, in-service inspection of a primary heat transfer tube bundle can be performed, deposits such as graphite dust and the like in the heat transfer tube bundle can be cleaned, and heat transfer efficiency is guaranteed not to be reduced.
Each turning seal head 13 is a detachable device, and after being detached, in-service inspection, pipe plugging, cleaning and maintenance of the two-loop heat transfer flow channel can be carried out. The main feed water output by the main feed water system 2-1 enters the first-stage heat exchange assembly 17-1 through the main feed water inlet chamber 12, finally enters the main steam outlet chamber 11 through the seventh-stage heat exchange assembly 17-7, and finally enters the main steam system 2-2.
Each steering seal head 13 is communicated with a steam generator continuous blowdown system 20 through a steam generator continuous blowdown valve 19, and each steering seal head 13 is communicated with the steam generator accident discharge system 3 through a steam generator accident discharge valve group 18;
when a loop detects a humidity signal, an automatic protection action opens a steam generator accident discharge valve set 18, and during the startup of the set, in order to quickly heat the heat transfer matrix or reversely heat the loop, a continuous blowdown valve 19 of the steam generator is opened, and two loops of high-temperature water or steam are introduced from a main water supply system 2-1 or a main steam system 2-2 for heating; when the unit stops at the initial stage, in order to quickly cool the heat transfer matrix and reduce the helium temperature of the primary loop, low-temperature water is introduced from the main water supply system 2-1 for cooling by opening the continuous blowdown valve 19 of the steam generator.
Claims (8)
1. A high-temperature gas cooled reactor steam generator with a blowdown function is characterized by comprising a steam generator base body (1), a main water supply system (2-1), a main steam system (2-2), a steam generator continuous blowdown system (20) and a steam generator accident discharge system (3);
a steam generator upper sealing head (10-1) is arranged at the opening at the top of the steam generator base body (1), a steam generator lower sealing head (8) is arranged at the opening at the bottom of the steam generator base body (1), and a steam generator bottom helium chamber (9) is formed in the steam generator lower sealing head (8);
a secondary loop medium heat exchange flow channel (14) is arranged in the steam generator base body (1), and a primary loop medium heat exchange flow channel (15) is formed between the secondary loop medium heat exchange flow channel (14) and the steam generator base body (1);
the outlet of the main water supply system (2-1) is communicated with the inlet of the secondary loop medium heat exchange flow passage (14), and the outlet of the secondary loop medium heat exchange flow passage (14) is communicated with the main steam system (2-2);
an upper end enclosure (10-1) of the steam generator is a cold helium outlet chamber (6) and a hot helium distribution chamber (7) through an inner shell partition plate (10-2) of the upper end enclosure, helium gas ascending flow channels (16) are arranged on two sides of a base body (1) of the steam generator, and an outlet of the hot helium distribution chamber (7) is communicated with the cold helium outlet chamber (6) through a loop medium heat exchange flow channel (15), a lower end enclosure (8) of the steam generator and the helium gas ascending flow channels (16);
the two-loop medium heat exchange flow channel (14) is communicated with a steam generator continuous blowdown system (20) through a steam generator continuous blowdown valve (19), and the two-loop medium heat exchange flow channel (14) is communicated with a steam generator accident discharge system (3) through a steam generator accident discharge valve group (18).
2. The high temperature gas cooled reactor steam generator with blowdown function as claimed in claim 1, wherein the side of the steam generator base (1) is provided with a principal feedwater inlet chamber (12); the outlet of the main water supply system (2-1) is communicated with the inlet of the two-loop medium heat exchange flow passage (14) through a main water supply inlet chamber (12).
3. The high temperature gas cooled reactor steam generator with blowdown function as claimed in claim 1, wherein the side of the steam generator base body (1) is provided with a main steam outlet chamber (11); the outlet of the two-loop medium heat exchange flow passage (14) is communicated with the main steam system (2-2) through a main steam outlet chamber (11).
4. The high-temperature gas cooled reactor steam generator with the pollution discharge function according to claim 1, wherein the two-loop medium heat exchange flow channel (14) comprises a first-stage heat exchange assembly (17-1), a second-stage heat exchange assembly (17-2), a third-stage heat exchange assembly (17-3), a fourth-stage heat exchange assembly (17-4), a fifth-stage heat exchange assembly (17-5), a sixth-stage heat exchange assembly (17-6) and a seventh-stage heat exchange assembly (17-7) which are sequentially communicated, and adjacent two-stage heat exchange assemblies are communicated through a steering seal head (13).
5. The high-temperature gas cooled reactor steam generator with the pollution discharge function according to claim 1, wherein an upper head (10-1) of the steam generator, an inner shell partition plate (10-2) of the upper head and a lower head (8) of the steam generator are all detachable structures.
6. The high temperature gas cooled reactor steam generator with blowdown function of claim 4, wherein each turn over head (13) is communicated with the steam generator continuous blowdown system (20) through the steam generator continuous blowdown valve (19).
7. The high temperature gas cooled reactor steam generator with blowdown function of claim 4, wherein each turn over head (13) is communicated with the steam generator accident discharge system (3) through a steam generator accident discharge valve set (18).
8. The high temperature gas cooled reactor steam generator with blowdown function of claim 4, wherein each turn over head (13) is a detachable device.
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CN202110991386.7A CN113719817A (en) | 2021-08-26 | 2021-08-26 | High-temperature gas cooled reactor steam generator with blowdown function |
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Citations (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0146305A2 (en) * | 1983-12-19 | 1985-06-26 | The Babcock & Wilcox Company | Controlling leaks between primary and secondary circuits of a steam generator of a pressurised water reactor system |
JP2010266131A (en) * | 2009-05-15 | 2010-11-25 | Mitsubishi Heavy Ind Ltd | Steam generator scale adhesion suppressing method |
CN108682461A (en) * | 2018-05-15 | 2018-10-19 | 中国核电工程有限公司 | A kind of passive air cooling system of containment for small-sized heap |
CN109395667A (en) * | 2017-08-18 | 2019-03-01 | 上海浦景化工技术股份有限公司 | A kind of axial-radial flow reactor for CO carbonylation coupling synthesizing dimethyl oxalate |
CN109994230A (en) * | 2019-04-12 | 2019-07-09 | 西安热工研究院有限公司 | A kind of passive dump of nuclear power station steam generator and cooling system and method |
CN209591545U (en) * | 2019-02-22 | 2019-11-05 | 西安热工研究院有限公司 | A kind of secondary circuit security system for reactor emergency shut-down |
CN112489831A (en) * | 2020-11-20 | 2021-03-12 | 西安热工研究院有限公司 | Testing device for functional verification of steam generator accident discharge system |
CN113205894A (en) * | 2021-04-29 | 2021-08-03 | 西安热工研究院有限公司 | High-temperature gas cooled reactor primary loop device |
-
2021
- 2021-08-26 CN CN202110991386.7A patent/CN113719817A/en active Pending
Patent Citations (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0146305A2 (en) * | 1983-12-19 | 1985-06-26 | The Babcock & Wilcox Company | Controlling leaks between primary and secondary circuits of a steam generator of a pressurised water reactor system |
JP2010266131A (en) * | 2009-05-15 | 2010-11-25 | Mitsubishi Heavy Ind Ltd | Steam generator scale adhesion suppressing method |
CN109395667A (en) * | 2017-08-18 | 2019-03-01 | 上海浦景化工技术股份有限公司 | A kind of axial-radial flow reactor for CO carbonylation coupling synthesizing dimethyl oxalate |
CN108682461A (en) * | 2018-05-15 | 2018-10-19 | 中国核电工程有限公司 | A kind of passive air cooling system of containment for small-sized heap |
CN209591545U (en) * | 2019-02-22 | 2019-11-05 | 西安热工研究院有限公司 | A kind of secondary circuit security system for reactor emergency shut-down |
CN109994230A (en) * | 2019-04-12 | 2019-07-09 | 西安热工研究院有限公司 | A kind of passive dump of nuclear power station steam generator and cooling system and method |
CN112489831A (en) * | 2020-11-20 | 2021-03-12 | 西安热工研究院有限公司 | Testing device for functional verification of steam generator accident discharge system |
CN113205894A (en) * | 2021-04-29 | 2021-08-03 | 西安热工研究院有限公司 | High-temperature gas cooled reactor primary loop device |
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Application publication date: 20211130 |