CN211906974U - Integrated nuclear reactor primary loop heat exchanger - Google Patents
Integrated nuclear reactor primary loop heat exchanger Download PDFInfo
- Publication number
- CN211906974U CN211906974U CN202020047682.2U CN202020047682U CN211906974U CN 211906974 U CN211906974 U CN 211906974U CN 202020047682 U CN202020047682 U CN 202020047682U CN 211906974 U CN211906974 U CN 211906974U
- Authority
- CN
- China
- Prior art keywords
- heat exchange
- cylinder
- heat exchanger
- reactor
- inner cylinder
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000004804 winding Methods 0.000 claims description 2
- 239000012530 fluid Substances 0.000 abstract description 3
- 238000009825 accumulation Methods 0.000 abstract description 2
- 238000001556 precipitation Methods 0.000 abstract description 2
- 238000007689 inspection Methods 0.000 description 5
- 238000010438 heat treatment Methods 0.000 description 4
- 238000004519 manufacturing process Methods 0.000 description 4
- XLYOFNOQVPJJNP-ZSJDYOACSA-N water-d2 Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 241000893018 Armeria Species 0.000 description 1
- 210000003733 Optic Disk Anatomy 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000002035 prolonged Effects 0.000 description 1
Images
Classifications
-
- 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
- Y02E30/30—Nuclear fission reactors
Abstract
The utility model relates to an integration nuclear reactor return circuit heat exchanger belongs to nuclear reactor technical field. The reactor comprises an outer cylinder, a middle cylinder, an inner cylinder, a spiral baffle plate and a reactor core, wherein the inner cylinder, the middle cylinder and the outer cylinder are sequentially arranged between an annular bottom plate and an annular top plate, the reactor core is arranged in the inner cylinder, a heat exchange tube is arranged in a cavity between the inner cylinder and the middle cylinder, a heat exchange medium in the reactor core and a heat exchange medium in the heat exchange tube form a loop of the integrated nuclear reactor, and the spiral baffle plate is welded on the outer wall of the inner cylinder. The utility model eliminates the dead zone which can not be utilized between the small heat exchangers, increases the area of the pipe distribution area of the heat exchange pipe, and improves the efficiency of the reactor; the spiral baffle plate inhibits the dirt accumulation and precipitation of shell pass fluid and prolongs the service life of the heat exchanger. The heat exchanger increases the effective length of the heat exchange tube, and reduces the equipment cost while improving the heat exchange efficiency of the reactor.
Description
Technical Field
The utility model relates to a primary loop heat exchanger of an integrated nuclear reactor, wherein when the reactor is used for heat supply, a primary loop is a heat exchanger; when the reactor is directly used for generating electricity, a loop can be an evaporator, and the reactor belongs to the technical field of nuclear reactors.
Background
The integrated nuclear reactor has heat exchanger, fuel assembly, control rod and other parts integrated inside the pressure container of the reactor, and the pressure container constitutes the main body of the pressure boundary of the loop. A heat exchanger is a heat exchange device that connects and isolates a reactor coolant loop and two loops. The heat exchanger designed in the past, for example, a split type U-shaped pipe heat exchanger adopted by a nuclear power engineering 24 th volume 2 nd phase 200MW low-temperature nuclear heat supply reactor, a split type straight pipe heat exchanger adopted by a nuclear power engineering 11 th volume 6 th phase 5MWTHR main heat exchanger, a nuclear power engineering 33 th volume 1 st phase multipurpose heavy water research reactor main heat exchanger adopts a sleeve pipe type structure, and a high-temperature gas cooled reactor adopts a spiral pipe type evaporator, the structure of which is shown in fig. 1 and 2, wherein in fig. 1 and 2, a is a pressure vessel, b is a heat exchanger, c is a second loop pipe orifice, and d is a reactor core. It can be seen from the figure that the existing split type U-shaped tube heat exchanger has the defects of difficult in-service inspection, difficult manufacture, incapability of effectively preventing tube flow vibration and the like except for the straight tube type scheme, and the existing straight tube type heat exchanger has low heat exchange efficiency. Therefore, the heat exchanger needs to be redesigned, and the problems of in-service inspection, pipe flow vibration, low heat exchange efficiency and the like which cannot be realized by the conventional scheme are solved.
Disclosure of Invention
The utility model aims at providing an integration nuclear reactor return circuit heat exchanger to make the heat exchanger can realize effectively preventing the pipe flow vibration at the inspection of labour, provide more excellent, safer heat exchanger for integration nuclear reactor.
The utility model provides an integrated nuclear reactor primary circuit heat exchanger, which comprises an annular bottom plate, an annular top plate, an outer cylinder, a middle cylinder, an inner cylinder, a spiral baffle plate and a reactor core, wherein the inner cylinder, the middle cylinder and the outer cylinder are coaxially arranged between the annular bottom plate and the annular top plate from inside to outside in sequence; the reactor core is arranged in the inner cylinder, a heat exchange tube is arranged in a cavity between the inner cylinder and the middle cylinder, and a heat exchange medium in the reactor core and a heat exchange medium in the heat exchange tube form a primary loop of the integrated nuclear reactor; the spiral baffle plate spirally rises along the outer wall of the inner cylinder body and is welded on the outer wall of the inner cylinder body in a winding manner, and a heat exchange medium in the spiral baffle plate is communicated with a heat exchange medium in a cavity between the inner cylinder body and the middle cylinder body; the cavity between the middle cylinder and the outer cylinder is a two-loop of the integrated nuclear reactor, and the upper part of the outer cylinder is provided with two-loop inlet pipes and two-loop outlet pipes; the outer cylinder and the pressure vessel cylinder are connected into a whole through an annular top plate and an annular bottom plate, the boundary of the pressure vessel in the nuclear reactor is used as the boundary of the outer cylinder of the heat exchanger, and the heat exchanger is a part of the reactor pressure vessel.
The utility model provides an integration nuclear reactor return circuit heat exchanger, its advantage:
1. the utility model discloses an integration nuclear reactor return circuit heat exchanger replaces many little heat exchangers in nuclear reactor type such as similar 5MW THR, 200MW low temperature nuclear heating reactor with an annular heat exchanger, has eliminated the blind spot that can not be utilized between the little heat exchanger, has increased the regional area of pipe arrangement of heat exchange tube, has improved the heating efficiency of reactor.
2. The utility model discloses an integration nuclear reactor return circuit heat exchanger, the pressure vessel border in the nuclear reactor is as the border of the outer barrel of heat exchanger, the heat exchanger is reactor pressure vessel's partly promptly, do not need other supports and location, two return circuits of heat exchanger go out, the entry is direct stretches out at the outer wall, 5MW THR has been avoided, 200MW low temperature nuclear heat supply piles etc. have had nuclear reactor main heat exchanger to rely on two return circuits to go out, the problem that the entry supported, more can guarantee two return circuits and go out, the position accuracy of entry, main heat exchanger weight has been avoided simultaneously to two return circuits go out, the extra load that the entry caused, space and material have been practiced thrift for nuclear reactor's construction, the equipment cost is reduced.
3. The utility model discloses a return circuit heat exchanger, wherein the quantity ratio 5MW THR of annular roof and annular bottom plate in the heat exchanger and multipurpose heavy water research pile in the straight tube formula or bushing type heat exchanger reduce half, have reduced total material and annular roof and annular bottom plate's processing cost. Meanwhile, two loop cavities in a straight tube type or double-tube type heat exchanger are omitted in the main heat exchanger, and the outlets and inlets of the two loops are arranged on the outer wall, so that a certain height is saved, the effective length of the heat exchange tube is increased, the heat supply efficiency of the nuclear heat supply reactor is improved, and the manufacturing cost is saved by more than half.
4. The loop heat exchanger of the integrated nuclear reactor of the utility model winds the spiral baffle plate outside the inner cylinder at the secondary side to form continuous support for the tube bundle of the heat exchanger, thereby reducing the vibration induced by fluid; the spiral baffle plate is a continuous curved surface, so that the water in the middle loop flows in a spiral plunger manner, no flow dead zone exists, and the heat transfer capacity is improved; the spiral baffle structure can effectively inhibit the dirt accumulation and precipitation of shell pass fluid, and the service life of the main heat exchanger is prolonged. Compared with the existing heat exchanger, the heat exchanger has a simple structure and reduces flow resistance. Primary loop heat exchanger
5. The utility model discloses a nuclear reactor of integration return circuit heat exchanger can realize the inspection on labour of heat exchanger, when the heat exchange tube goes wrong, can carry out stifled pipe and overhaul. And the existing small heat exchangers of nuclear reactors like 5MW THR and 200MW low-temperature nuclear heating reactors are not easy to realize in-service inspection and pipe blockage maintenance.
Drawings
Fig. 1 is a schematic diagram of a conventional 200MW nuclear heating reactor and heat exchanger.
Fig. 2 is a top view of fig. 1.
Fig. 3 is a schematic structural diagram of a primary loop heat exchanger of an integrated nuclear reactor.
Fig. 4 is a top view of fig. 3.
FIG. 5 is a schematic view of the installation of the helical baffle.
In fig. 1 and 2, a is a pressure vessel, b is a heat exchanger, c is a secondary loop nozzle, and d is a core.
In fig. 3 and 4, 1 is an annular bottom plate, 2 is an outer cylinder, 3 is an intermediate cylinder, 4 is a two-circuit outlet pipe, 5 is a two-circuit inlet pipe, 6 is a heat exchange pipe, 7 is an inner cylinder, 8 is a spiral baffle plate, 9 is an annular top plate, and 10 is a core.
In fig. 5, 11 is a tube hole.
Detailed Description
The utility model provides an integrated nuclear reactor primary loop heat exchanger, the structure of which is shown in figure 3 and figure 4, comprising an annular bottom plate 1, an annular top plate 9, an outer cylinder 2, a middle cylinder 3, an inner cylinder 7, a spiral baffle plate 8 and a reactor core 10, wherein the inner cylinder 7, the middle cylinder 3 and the outer cylinder 2 are coaxially arranged between the annular bottom plate 1 and the annular top plate 9 from inside to outside in sequence; the reactor core 10 is arranged in the inner cylinder 7, a heat exchange tube 6 is arranged in a cavity between the inner cylinder 7 and the middle cylinder 3, and a heat exchange medium in the reactor core 10 and a heat exchange medium in the heat exchange tube 6 form a loop of the integrated nuclear reactor; the spiral baffle plate 8 is spirally upwards coiled and welded on the outer wall of the inner cylinder 7 along the outer wall of the inner cylinder 7, and as shown in fig. 3, a heat exchange medium in the spiral baffle plate 8 is communicated with a heat exchange medium in a cavity between the inner cylinder 7 and the middle cylinder 3; the cavity between the middle cylinder 3 and the outer cylinder 2 is a two-loop of the integrated nuclear reactor, and the upper part of the outer cylinder 2 is provided with a two-loop inlet pipe 5 and a two-loop outlet pipe 4; the outer cylinder 2 and the pressure vessel cylinder are connected into a whole through an annular top plate 9 and an annular bottom plate 1, and the boundary of the pressure vessel in the nuclear reactor is used as the boundary of the outer cylinder of the heat exchanger, namely a part of the reactor pressure vessel.
The utility model provides a working principle and the working process of integration nuclear reactor primary circuit heat exchanger are introduced in detail below with the accompanying drawing:
the overall structure is as follows: the primary loop heat exchangers adopt an annular tube bundle type structure and are used as the middle section of the pressure container, and the outer cylinder body 2 and the pressure container share a section of shell; the annular tube bundle is positioned in an annular space between the middle cylinder 3 and the inner cylinder 7; the upper ends of the heat exchanger outer cylinder 2, the middle cylinder 3 and the inner cylinder 7 are all welded with an annular top plate 9; the inner cylinder 7 and the outer cylinder 2 are pressure-bearing cylinders, and the lower ends of the two pressure-bearing cylinders are welded with the annular bottom plate 1; the spiral baffle plate 8 is coiled and welded on the outer wall of the inner cylinder 7; the annular top plate 9, the annular bottom plate 1 and the spiral baffle plate 8 are provided with pipe holes with the same number as the heat exchange pipes 6, and the pipe holes are uniformly distributed along the annular area; the heat exchange tube 6 penetrates through the annular top plate 9, the spiral baffle plate 8 and the tube hole on the annular bottom plate 1 and is welded with the annular top plate 9 and the annular bottom plate 1; a secondary loop inlet pipe 5 is welded with the outer cylinder 2 of the main heat exchanger, and a secondary loop outlet pipe 4 is welded with the middle cylinder 3 (non-pressure-bearing cylinder); the inlet and outlet pipes of the two loops are respectively connected to the two loop systems.
The design of the flow channel is as follows: the main heat exchanger adopts a single straight tube heat transfer surface, only has an annular top plate and an annular bottom plate, and has two flow channels for heat transfer, an inner flow channel (loop water) in the heat exchange tube 6 and an outer flow channel (middle loop water) on the spiral baffle plate 8 outside the heat exchange tube 6; the two loops rise around the spiral baffle plate, and the flow passage in the pipe and the flow passage outside the pipe perform countercurrent heat exchange.
Structure and manufacturing assembly: the heat exchanger adopts a single straight pipe structure, the connection mode of the heat exchange pipe, the annular top plate and the annular bottom plate is strength welding and strength expansion, and the sequence of assembling and expansion welding can be determined by a manufacturing unit.
Claims (1)
1. A primary loop heat exchanger of an integrated nuclear reactor is characterized by comprising an annular bottom plate, an annular top plate, an outer cylinder, an intermediate cylinder, an inner cylinder, a spiral baffle plate and a reactor core, wherein the inner cylinder, the intermediate cylinder and the outer cylinder are coaxially arranged between the annular bottom plate and the annular top plate from inside to outside in sequence; the reactor core is arranged in the inner cylinder, a heat exchange tube is arranged in a cavity between the inner cylinder and the middle cylinder, and a heat exchange medium in the reactor core and a heat exchange medium in the heat exchange tube form a primary loop of the integrated nuclear reactor; the spiral baffle plate spirally rises along the outer wall of the inner cylinder body and is welded on the outer wall of the inner cylinder body in a winding manner, and a heat exchange medium in the spiral baffle plate is communicated with a heat exchange medium in a cavity between the inner cylinder body and the middle cylinder body; the cavity between the middle cylinder and the outer cylinder is a two-loop of the integrated nuclear reactor, and the upper part of the outer cylinder is provided with two-loop inlet pipes and two-loop outlet pipes; the outer cylinder and the pressure vessel cylinder are connected into a whole through an annular top plate and an annular bottom plate, the boundary of the pressure vessel in the nuclear reactor is used as the boundary of the outer cylinder of the heat exchanger, and the heat exchanger is a part of the reactor pressure vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202020047682.2U CN211906974U (en) | 2020-01-09 | 2020-01-09 | Integrated nuclear reactor primary loop heat exchanger |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202020047682.2U CN211906974U (en) | 2020-01-09 | 2020-01-09 | Integrated nuclear reactor primary loop heat exchanger |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN211906974U true CN211906974U (en) | 2020-11-10 |
Family
ID=73296667
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202020047682.2U Active CN211906974U (en) | 2020-01-09 | 2020-01-09 | Integrated nuclear reactor primary loop heat exchanger |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN211906974U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113689964A (en) * | 2021-08-30 | 2021-11-23 | 西安交通大学 | Main heat-waste heat integrated heat exchanger of small nuclear reactor |
-
2020
- 2020-01-09 CN CN202020047682.2U patent/CN211906974U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113689964A (en) * | 2021-08-30 | 2021-11-23 | 西安交通大学 | Main heat-waste heat integrated heat exchanger of small nuclear reactor |
| CN113689964B (en) * | 2021-08-30 | 2022-12-09 | 西安交通大学 | Main heat-waste heat integrated heat exchanger of small nuclear reactor |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105457563B (en) | Isothermal shift reactor with built-in tube bundle | |
| US3941187A (en) | Consolidated nuclear steam generator | |
| CN103240037B (en) | A kind of ellipse spiral tubular type microchannel gas-solid phase reaction device | |
| CN211906974U (en) | Integrated nuclear reactor primary loop heat exchanger | |
| CN201014816Y (en) | Double circulation heat storage water tank of solar energy water heater | |
| CN101620892B (en) | Structural design of loop system of high-power pressurized water reactor nuclear power station | |
| CA1080691A (en) | Helical coil steam generator | |
| CN201129943Y (en) | Fixed tube sheet warm water circulating type gasifier | |
| US4124064A (en) | Consolidated nuclear steam generator | |
| US4174123A (en) | Vessel penetration apparatus | |
| CN101065620B (en) | A water heater and a method of operating same | |
| CN111081397A (en) | Integrated nuclear reactor primary loop heat exchanger | |
| CN212340041U (en) | Flow guide structure at inlet of upper shell pass of wound tube type heat exchanger | |
| CN105180687A (en) | Double-shell-pass shell-and-tube heat exchanger with baffle rods | |
| CN202346974U (en) | External heat collector | |
| CN102831941B (en) | 0-shaped lead-bismuth heat exchange device | |
| CN201503005U (en) | Primary side four-chamber two-way flow heat exchange tube pressured water reactor steam generator | |
| CN101279227A (en) | Membrane type wall reactor | |
| CN104248939B (en) | Methanol oxidizer in silver catalyst process formaldehyde device | |
| CN201186210Y (en) | Vertical type water-cooling tube box type reactor | |
| CN113188344B (en) | Additive manufacturing heat exchanger with half' loop pipe type baffling and drainage structure | |
| CN205299489U (en) | Cold grey ware of diaphragm type wall | |
| CN201548103U (en) | Raw gas heat-exchange facility for natural gas hydrogen production plant | |
| CN201200885Y (en) | Membrane type wall-shell type reactor | |
| CN214120852U (en) | Spiral coil pipe type heat exchange tube |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant |