CN210667820U - Reactor body structure of nuclear steam supply system with double-layer sleeve structure - Google Patents
Reactor body structure of nuclear steam supply system with double-layer sleeve structure Download PDFInfo
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- CN210667820U CN210667820U CN201920729848.6U CN201920729848U CN210667820U CN 210667820 U CN210667820 U CN 210667820U CN 201920729848 U CN201920729848 U CN 201920729848U CN 210667820 U CN210667820 U CN 210667820U
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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
- Y02E30/30—Nuclear fission reactors
Abstract
The utility model provides a reactor body structure of a nuclear steam supply system with a double-layer sleeve structure, which is respectively connected with at least one main pump and at least one steam generator through the double-layer sleeve structure, wherein the reactor body structure respectively forms a loop with one steam generator and one main pump; the reactor body structure comprises a pressure vessel, an in-reactor component, a control rod driving mechanism, an in-reactor instrument assembly and a reactor core fuel assembly; the pressure vessel is respectively connected with the main pump and the steam generator through a double-layer sleeve structure. The utility model discloses can ensure the circulation of the coolant in the nuclear reactor, be convenient for again realize the compact of nuclear steam supply system and arrange, improve heat exchange efficiency, and be convenient for install and dismantle, the security is good.
Description
Technical Field
The utility model relates to a nuclear power field especially relates to nuclear steam supply system's reactor body structure with double-deck sleeve structure.
Background
A nuclear steam supply system is a system for generating steam in a nuclear power plant by using heat energy generated by a fission reaction of nuclear fuel in a nuclear reactor, and is generally used for generating electricity, driving and supplying heat, and mainly includes a nuclear reactor, a steam generator, a primary coolant system and auxiliary systems thereof.
During operation of a nuclear steam supply system, a coolant is required to constantly carry out a large amount of heat generated by fission in a nuclear reactor core and to control the temperature in the nuclear reactor within a desired range. Taking a two-loop nuclear steam supply system as an example, after being heated in a nuclear reactor, coolant is sent into a steam generator by a main circulating pump, and feedwater on the other side of the steam generator is heated to be changed into steam which is sent to a steam turbine generator unit to drive the steam turbine generator unit; and the coolant condensed by the condenser of the steam turbine generator unit is sent into the nuclear reactor again, and the circulation is carried out.
However, in the prior art, a long pipeline is usually used for connecting the nuclear reactor with other equipment such as a steam generator to transport the coolant, which not only reduces the heat exchange efficiency, but also requires an inlet connection pipe and an outlet connection pipe for the nuclear reactor, and the whole system occupies a large space and cannot meet the requirements of the marine use environment.
SUMMERY OF THE UTILITY MODEL
The utility model provides a reactor body structure of nuclear steam supply system with double-deck sleeve structure, it has compact structure's characteristics, and heat exchange efficiency is high, is convenient for install and dismantle, can satisfy ocean service environment.
The utility model provides a reactor body structure of a nuclear steam supply system with a double-layer sleeve structure, which is connected with at least one main pump and at least one steam generator through the double-layer sleeve structure respectively, and the reactor body structure forms a loop with the steam generator and the main pump respectively; the reactor body structure comprises a pressure vessel, an in-reactor component, a control rod driving mechanism, an in-reactor instrument assembly and a reactor core fuel assembly; the pressure container is respectively connected with the main pump and the steam generator through a double-layer sleeve structure; wherein:
the double-layer sleeve structure comprises an inner pipe and an outer pipe positioned outside the inner pipe, the outer pipe is formed by inlet and outlet connecting pipes of the pressure container, and the inner pipe is arranged inside the outer pipe;
the reactor internals comprise a lower reactor internals with a hanging basket, an upper reactor internals and a ring cavity structure outside the hanging basket; the annular cavity structure is a structure similar to a cone cylinder, is arranged on the outer side of the hanging basket and the inner side of the pressure container, is fixed with the inner wall of the pressure container, is provided with a sealing element to realize sealing with the inner wall of the pressure container, and is provided with openings corresponding to the double-layer sleeve;
each inner pipe is detachably arranged on the annular cavity structure and is positioned in the outer pipe, and an inner annular cavity is formed between each inner pipe and the annular cavity structure; the internal annular cavity is communicated with an inner sleeve of the double-layer sleeve structure at the main pump side, an annular cavity of a pressure vessel descending section and an outlet inner sleeve of the double-layer sleeve structure at the steam generator side;
the annular cavity structure and the inner wall of the pressure vessel form an external annular cavity, and the external annular cavity is communicated with an outer pipe of the double-layer sleeve structure on the pump side and an outer pipe of the double-layer sleeve structure on the steam generator side.
Preferably, the coolant enters an inner annular cavity of the annular cavity structure from an inner sleeve runner of the double-layer sleeve structure on the pump side, then enters a lower end enclosure along a descending annular cavity between the pressure vessel and the hanging basket, enters the reactor core after passing through the flow distribution device, flows into an upper cavity after being heated by the reactor core, and then enters an inner sleeve runner of the double-layer sleeve structure on the steam generator side through a hanging basket outlet nozzle to enter the steam generator; the coolant after heat exchange of the steam generator flows back to the main pump through the flow channels of the outer sleeve on the side of the steam generator, the outer ring cavity of the ring cavity structure and the outer sleeve on the side of the pump.
Preferably, the annular cavity structure is fixed on the inner side of the pressure vessel through a pin connection or a welding mode, and the annular cavity structure and the inner pipe form sealing fit through a mechanical connecting handle and a sealing piece.
Preferably, a hole is formed in the position, corresponding to the outlet connecting pipe of the pressure vessel, of the hanging basket, the hole is communicated with an inner pipe of the double-layer sleeve structure on the steam generator side, and the inner pipe and the annular cavity structure are sealed at the position of the hole.
Preferably, the pressure vessel is provided with a supporting shoulder, the upper reactor internals comprise a guide pipe supporting plate which is positioned at the top of the hanging basket, and the flange of the hanging basket and the flange of the guide pipe supporting plate are sequentially superposed on the supporting shoulder of the pressure vessel and positioned above the annular cavity structure; through holes are formed in the corresponding positions of the hanging basket flange and the guide pipe support plate flange, and a spray pipe structure is installed in the through holes and communicated with the inner ring cavity; when coolant from a main pump enters the pressure vessel through the inner sleeve, a part of flow enters the interior of the upper end socket of the pressure vessel through the nozzle structure at the flange of the hanging basket and the flange of the support plate of the guide pipe, flows downwards to the upper cavity of the reactor, and flows out of the reactor through the outlet of the hanging basket.
Preferably, a safety injection nozzle is arranged near the double-layer sleeve of the pressure vessel, a hole is formed in the corresponding position of the annular cavity structure, a through pipe structure is arranged to directly penetrate through the annular cavity structure to be matched and sealed with the safety injection nozzle, and the safety injection system is directly injected into the reactor core through the safety injection nozzle, the inner straight pipe structure and the inner cavity of the annular cavity structure to prevent the reactor core from being melted under the accident of loss of coolant in the reactor core.
Preferably, the control rod driving mechanism is provided with a rod dropping auxiliary assembly to ensure that the rod can be dropped smoothly under working conditions of swinging, inclining and the like in the marine environment, and the requirement of rod dropping time is met.
Preferably, the control rod drive mechanism is provided with a rollover locking device to ensure that the control rod assembly is not drawn out of the reactor core in the event of ocean rollover.
Preferably, the in-core instrument measuring assembly adopts an integrated detector assembly, the neutron fluence rate of the reactor core and the outlet temperature of the reactor core are measured simultaneously, and the number of detectors is reduced.
Preferably, the in-stack instrument assembly is led out from the group of the top of the stack in a centralized mode.
Implement the embodiment of the utility model provides a, following beneficial effect has:
according to the above description, the utility model discloses a double-deck sleeve structure is connected in order to carry out the circulation transport of coolant with other equipment such as steam generator among the nuclear steam supply system, and this double-deck sleeve structure's outer tube can be direct and other equipment such as steam generator butt welding form the pipeline, and the inner tube then borrows by ring cavity structural mounting to support, can reduce the probability that the coolant loses accident (LOCA) and take place, can realize nuclear steam supply system's compact arrangement again, improves heat exchange efficiency. Particularly, the utility model supports the inner pipe by arranging the annular cavity structure on the pressure vessel, so that the double-layer sleeve structure is more stable, and the inner pipe of the double-layer sleeve structure is detachably arranged on the inner pipe, thereby not only meeting the maintenance and disassembly requirements of the inner pipe, but also ensuring that the disassembly of the inner pipe is mutually independent with the hoisting of the internal stacking components such as the hanging basket and the like;
meanwhile, through holes are formed in the corresponding positions of the hanging basket flange and the guide pipe support plate flange, and a spray pipe structure is installed at the through holes, when coolant from a main pump enters the pressure vessel through the inner sleeve, main flow enters the reactor core through the annular cavity of the descending section of the pressure vessel for heat exchange, and a small part of flow enters the upper end socket of the pressure vessel through the spray pipe structure at the positions of the hanging basket flange and the guide pipe support plate flange and flows downwards to the upper cavity of the reactor and flows out of the reactor through a hanging basket outlet;
in addition, a safety injection nozzle is arranged near the double-layer sleeve of the pressure vessel, a hole is formed in the corresponding position of the annular cavity structure, a penetrating pipe structure is designed to penetrate through the annular cavity structure and the wall of the pressure vessel to be matched and sealed with the safety injection nozzle, and the safety injection system is directly injected into the reactor core through the safety injection nozzle, the inner straight pipe structure and the inner cavity of the annular cavity structure to prevent the reactor core from being melted under the loss of coolant accident of the reactor core.
The utility model discloses compact structure, heat transfer are effectual, and the installation and the dismantlement of being convenient for very much, and the security is high, the service environment of very suitable ocean.
Drawings
Fig. 1 is a schematic view of an operating environment of a reactor body structure of a nuclear steam supply system having a double-layer sleeve structure according to the present invention;
FIG. 2 is a schematic view of a structural portion of the reactor body taken along the A-A direction in FIG. 1;
FIG. 3 is a partial schematic view of FIG. 2;
fig. 4 is a partial schematic view of the reactor body structure taken along the direction B-B in fig. 1.
Detailed Description
The utility model discloses reactor body structure is equipped with double-deck sleeve structure, is connected with other equipment such as steam generator in the nuclear steam supply system via this double-deck sleeve structure, carries out the circulating transport of coolant. The double-layer sleeve structure comprises an inner pipe and an outer pipe sleeved outside the inner pipe, wherein the outer pipe is formed by an inlet connecting pipe of a pressure container of a nuclear reactor, the inner pipe is detachably arranged in the outer pipe, coolant flows into the pressure container of the nuclear reactor through a first channel between the outer pipe and the inner pipe, and after the coolant is heated, the coolant flows out of the pressure container of the nuclear reactor through a second channel in the inner pipe. The utility model discloses set up the ring cavity structure on the outer wall of nuclear reactor's hanging flower basket, the inner tube is that detachably sets up in this ring cavity structure and lies in the outer tube, and the inner tube is through this ring cavity structure and the inside intercommunication of hanging flower basket for the coolant can be by the inside inner tube that flows in through the ring cavity structure of hanging flower basket, and then flows nuclear reactor's pressure vessel. The annular structure is not only used for detachably mounting the inner tube thereon, but also forms an inner cavity with the outer wall of the basket, so as to sufficiently collect the coolant heated by the core and guide the coolant into the inner tube to flow out of the nuclear reactor, which will be described in detail by way of example.
As shown in fig. 1, the present invention provides a schematic diagram of an operating environment of a reactor body structure of a nuclear steam supply system having a double-layer sleeve structure; as shown in fig. 2 to 4. The reactor body structure 1 is connected with at least one main pump 7 and at least one steam generator 8 through a double-layer sleeve structure 10, and the reactor body structure 1 and the steam generator 8 and the main pump 7 form a loop; and the pressure stabilizer 9 is connected to any one of the two sets of steam generators 8 and the main pump 7 for adjusting and maintaining the pressure in a loop formed by the reactor body structure 1, the steam generators 8 and the main pump 7.
As shown in fig. 2, a schematic view of the structural portion of the reactor body taken along the a-a direction in fig. 1 is shown; in the present embodiment, the reactor body structure 1 includes a pressure vessel 20, internals, control rod drive mechanisms 50, in-core instrumentation assemblies 60, and core fuel assemblies 70; the pressure vessel 20 is connected with the main pump 7 and the steam generator 8 through a double-layer sleeve structure 10, in fig. 1, the left side of the pressure vessel 20 is connected with the main pump 7, and the right side of the pressure vessel 20 is connected with the steam generator 8; wherein:
the pressure vessel 20 is provided with an inner cavity 21 and an inlet connecting pipe communicated with the inner cavity 21, the inner cavity 21 is defined by a body 23 and an upper sealing head 24 of the pressure vessel 20, and a lower sealing head 25 is formed at the bottom of the body 23.
The internals are disposed in the internal cavity 21 of the pressure vessel 20 and include a lower internals, an upper internals, and a toroidal cavity structure 30. Wherein the lower reactor internals comprise a hanging basket 41, a lower grid plate 45 descending segment annular cavity 47 of a reactor core and a flow distribution device 44; the upper internals include a guide tube support plate 42 disposed on top of a basket 41, a guide tube assembly 43 disposed inside the basket 20, and an upper core grid plate 46, wherein a ring structure 30 and a drop ring 47 are disposed around the outside of the basket 41.
The annular cavity structure 30 is a structure similar to a cone cylinder, is arranged on the outer side of the hanging basket 41 and the inner side of the pressure container 20, is fixed with the inner wall of the pressure container 20, is provided with a sealing element to realize sealing with the inner wall of the pressure container 20, and is provided with openings corresponding to the double-layer sleeve 11;
the double-layer sleeve structure 10 comprises an inner pipe 11 and an outer pipe 12 positioned outside the inner pipe 11, the outer pipe 12 is formed by an inlet and outlet connecting pipe of the pressure container 20, and the inner pipe 11 is arranged inside the outer pipe 12;
each inner pipe 11 is detachably arranged on the annular cavity structure 30 and is positioned in the outer pipe 12, and an inner annular cavity 31 is formed between each inner pipe 11 and the annular cavity structure 30; the internal annular cavity 31 is communicated with an inner sleeve 11 of a double-layer sleeve structure at the main pump side, an annular cavity 47 of a pressure vessel descending section and an outlet inner sleeve 11 of a double-layer sleeve structure at the steam generator side;
the ring cavity structure 30 and the inner wall of the pressure vessel 20 form an outer ring cavity 32, and the outer ring cavity 32 is communicated with the outer pipe 12 of the pump side double-layer sleeve structure and the outer pipe 12 of the steam generator side double-layer sleeve structure.
More specifically, the flange 412 of the basket 41 is disposed on the support shoulder 27 of the pressure vessel 20 such that the basket 41 carries the core. The guide tube support plate 42 is placed on top of the basket 41 for supporting the guide tube assembly 43 with its flange 421 overlying the flange 412 of the basket 41. The core (not shown) is located between the core lower grid plate 45 and the core upper grid plate 46. The control rods and their drive mechanisms 50 are inserted into the core and extend out of the pressure vessel 20 through the upper head 24. The guide tube assembly 43 is used to insert control rods into the core and has one end extending into the upper core grid plate 46 and the other end extending into the upper head 24 through the guide tube support plate 42.
The in-core instrument assembly 60 is led out in a grouping and concentrated mode through the upper end enclosure 24, leakage caused by stress corrosion of welding seams of the lower end enclosure 25 can be avoided, the water loss probability of a reactor core is reduced, the number of holes of the upper end enclosure 24 can be reduced through the grouping and concentrated lead-out, and hole reinforcement and welding work of the upper end enclosure 24 is reduced.
The relative arrangement of the double-walled sleeve structure 10 and the annular chamber structure 30 will be described next. As shown in fig. 1, in the reactor body structure 1, the double-layer sleeve structure 10 includes an inner tube 11 and an outer tube 12 sleeved outside the inner tube 11, wherein a first channel 111 is formed in the inner tube 11, a second channel 121 is formed between the inner tube 11 and the outer tube 12, and the first channel 111 is isolated from the second channel 121. The outer tube 12 is formed by extending the pressure vessel 20 and communicates with the inner cavity 21 of the pressure vessel 20. In the present exemplary embodiment, the outer tube 12 is formed by an inlet connection of the pressure vessel 20, which can be welded directly to a further device 2, for example a steam generator. The inner tube 11 is detachably disposed on the annular cavity structure 30 and is located in the outer tube 12. On the steam generator side, a hole 410 is formed in the position, corresponding to the pressure vessel outlet connecting pipe, of the hanging basket 41, the hole 410 is communicated with the inner pipe 111 of the double-layer sleeve structure 10 on the steam generator side, and the inner pipe 111 and the annular cavity structure 30 are sealed at the position of the hole 410.
The annular cavity structure 30 is arranged on the outer wall of the hanging basket 41, and an inner annular cavity 31 is formed between the annular cavity structure 30 and the outer wall of the hanging basket 41 in the annular cavity structure 30. The annular cavity structure 30 is provided with an opening, one end of the inner tube 11 is detachably arranged in the opening, and a sealing fit is formed between the two. In this way, the coolant entering the inner ring cavity 31 can flow out of the reactor body structure 1 through the first passage 111 in the right inner tube 11, and enter other equipment (steam generator) connected to the reactor body structure 1. That is, the inner annular chamber 31 is in fluid communication with the first passage 111 of the inner tube 11, while being isolated from the second passage 121 between the inner tube 11 and the outer tube 12. The ring structure 30 and the inner tube 11 may be sealingly engaged by means of a mechanical connection stem in combination with a sealing member, and the ring structure 30 may be arranged on the pressure vessel 20 by means of a pin connection or welding. Therefore, the maintenance and disassembly requirements of the inner pipe 11 can be met, and the disassembly of the inner pipe 11 and the hoisting of the internal stacking components such as the hanging basket 41 are mutually independent.
Preferably, the annular chamber structure 30 is an annular structure disposed around the basket 41, and in this case, the inner annular chamber 31 is an annular chamber. The inner pipes 11 of the double-layer sleeve structures 10 arranged on the reactor body structure 1 according to requirements are all communicated with the inner ring cavity 31 in a fluid mode. The setting according to the requirement can be according to the connection requirement of the nuclear reactor and other equipment.
In the present invention, the pressure vessel 20 has a supporting shoulder 27, the upper reactor internals includes a guide tube supporting plate 42, the guide tube supporting plate 42 is located at the top of the hanging basket 41, the flange 412 of the hanging basket 41 and the flange 421 of the guide tube supporting plate 42 are sequentially overlapped on the supporting shoulder 27 of the pressure vessel and located above the annular cavity structure; the basket flange 412 and the guide pipe support plate flange 421 are provided with through holes at corresponding positions, the through holes are provided with the nozzle structures 48, the nozzle structures 48 are communicated with the inner annular cavity 31, and specifically, the nozzle structures 48 are communicated with the inner annular cavity through a gap 49 between the annular cavity structure 30 and the basket 41.
It can be understood that, in the present invention, the coolant from the main pump 7 enters the annular cavity structure 30 through the inner sleeve 11 flow channel of the double-layer sleeve structure on the pump side, then enters the lower head along the descending annular cavity 47 between the pressure vessel 30 and the hanging basket 41, enters the reactor core through the flow distribution device 44, flows into the upper chamber after being heated by the reactor core, and then enters the inner sleeve 111 flow channel of the double-layer sleeve structure on the steam generator side through the outlet nozzle of the hanging basket 41 to enter the steam generator 8; the coolant after heat exchange of the steam generator 8 flows back to the main pump 7 through the outer sleeve 12 on the side of the steam generator 8, the outer ring cavity 32 of the ring cavity structure 30 and the flow channel of the outer sleeve 12 on the side of the pump. Thus realizing the circulation and the delivery of the coolant.
Further, when coolant from the main pump 7 enters the pressure vessel 30 through the inner sleeve 11, a part of the flow enters the interior of the pressure vessel upper head 24 through the basket flange 412 and the nozzle structure 48 at the guide tube support plate flange 421, flows down to the reactor upper chamber and exits the reactor through the outlet of the basket 41, and the flow direction is shown by the dotted line in fig. 3.
So designed, the utility model discloses not only can carry out reactor body structure 1 with the coolant of the inside through core heating of hanging flower basket 41, be located that the coolant of the inside through core heating of hanging flower basket 41 flows out hanging flower basket 41 again through inner ring chamber 31 and gets into inner tube 11 by through-hole 411, can flow out reactor body structure 1.
Fig. 4 is a partial schematic view of the reactor body structure taken along the direction B-B in fig. 1. It can be understood that a safety injection nozzle 28 is arranged near the double-layer sleeve 10 of the pressure vessel 20, a hole is formed in the annular cavity structure 30 at a position corresponding to the hole, a through pipe structure 29 is arranged to directly penetrate through the annular cavity structure 30 to be matched and sealed with the safety injection nozzle 28, the through pipe structure 29 is a straight pipe with a flange at one end, in the event of core loss, a safety injection system is directly injected into the core through the safety injection nozzle 28, the inner straight pipe structure 29 and the inner cavity of the annular cavity structure 30 to prevent the core from melting, and the dashed line in fig. 4 shows the injection trend of the safety injection system.
Further, the utility model discloses in, control rod drive mechanism 50 is provided with the stick auxiliary assembly that falls to can fall the stick smoothly under the operating mode such as rocking, slope of ensureing under the marine environment, satisfy the stick time requirement that falls. Meanwhile, the control rod driving mechanism 50 is provided with a rollover locking device, so that the control rod assembly is ensured not to be drawn out of the reactor core under the condition of ocean rollover.
Meanwhile, the in-core instrument measuring assembly 60 adopts an integrated detector assembly, and simultaneously measures the reactor core neutron fluence rate and the reactor core outlet temperature, thereby reducing the number of detectors.
Implement the utility model discloses, following beneficial effect has:
according to the above description, the utility model discloses a double-deck sleeve structure is connected in order to carry out the circulation transport of coolant with other equipment such as steam generator among the nuclear steam supply system, and this double-deck sleeve structure's outer tube can be direct and other equipment such as steam generator butt welding form the pipeline, and the inner tube then borrows by ring cavity structural mounting to support, can reduce the probability that the coolant loses accident (LOCA) and take place, can realize nuclear steam supply system's compact arrangement again, improves heat exchange efficiency. Particularly, the utility model supports the inner pipe by arranging the annular cavity structure on the pressure vessel, so that the double-layer sleeve structure is more stable, and the inner pipe of the double-layer sleeve structure is detachably arranged on the inner pipe, thereby not only meeting the maintenance and disassembly requirements of the inner pipe, but also ensuring that the disassembly of the inner pipe is mutually independent with the hoisting of the internal stacking components such as the hanging basket and the like;
meanwhile, through holes are formed in the corresponding positions of the hanging basket flange and the guide pipe support plate flange, and a spray pipe structure is installed at the through holes, when coolant from a main pump enters the pressure vessel through the inner sleeve, main flow enters the reactor core through the annular cavity of the descending section of the pressure vessel for heat exchange, and a small part of flow enters the upper end socket of the pressure vessel through the spray pipe structure at the positions of the hanging basket flange and the guide pipe support plate flange and flows downwards to the upper cavity of the reactor and flows out of the reactor through a hanging basket outlet;
in addition, a safety injection nozzle is arranged near the double-layer sleeve of the pressure vessel, a hole is formed in the corresponding position of the annular cavity structure, a penetrating pipe structure is designed to penetrate through the annular cavity structure and the wall of the pressure vessel to be matched and sealed with the safety injection nozzle, and the safety injection system is directly injected into the reactor core through the safety injection nozzle, the inner straight pipe structure and the inner cavity of the annular cavity structure to prevent the reactor core from being melted under the loss of coolant accident of the reactor core.
The utility model discloses compact structure, heat transfer are effectual, and the installation and the dismantlement of being convenient for very much, and the security is high, the service environment of very suitable ocean.
The above description is only for the preferred embodiment of the present invention and should not be construed as limiting the scope of the claims, therefore, all other equivalent changes and modifications that do not depart from the spirit of the present invention should be included in the scope of the claims.
Claims (10)
1. A reactor body structure of a nuclear steam supply system with a double-layer sleeve structure is characterized in that the reactor body structure is respectively connected with at least one main pump and at least one steam generator through the double-layer sleeve structure, wherein the reactor body structure respectively forms a loop with one steam generator and one main pump; the reactor body structure comprises a pressure vessel, an in-reactor component, a control rod driving mechanism, an in-reactor instrument assembly and a reactor core fuel assembly; the pressure container is respectively connected with the main pump and the steam generator through a double-layer sleeve structure; the method is characterized in that:
the double-layer sleeve structure comprises an inner pipe and an outer pipe positioned outside the inner pipe, the outer pipe is formed by inlet and outlet connecting pipes of the pressure container, and the inner pipe is arranged inside the outer pipe;
the reactor internals comprise a lower reactor internals with a hanging basket, an upper reactor internals and a ring cavity structure outside the hanging basket; the annular cavity structure is a structure similar to a cone cylinder, is arranged on the outer side of the hanging basket and the inner side of the pressure container, is fixed with the inner wall of the pressure container, is provided with a sealing element to realize sealing with the inner wall of the pressure container, and is provided with openings corresponding to the double-layer sleeve;
each inner pipe is detachably arranged on the annular cavity structure and is positioned in the outer pipe, and an inner annular cavity is formed between each inner pipe and the annular cavity structure; the internal annular cavity is communicated with an inner sleeve of the double-layer sleeve structure at the main pump side, an annular cavity of a pressure vessel descending section and an outlet inner sleeve of the double-layer sleeve structure at the steam generator side;
the annular cavity structure and the inner wall of the pressure vessel form an external annular cavity, and the external annular cavity is communicated with an outer pipe of the double-layer sleeve structure on the pump side and an outer pipe of the double-layer sleeve structure on the steam generator side.
2. The reactor body structure of claim 1, wherein the coolant enters the inner annular cavity of the annular cavity structure from the inner sleeve runner of the double-layer sleeve structure at the pump side, then enters the lower end enclosure along the descending annular cavity between the pressure vessel and the hanging basket, enters the reactor core after passing through the flow distribution device, is heated by the reactor core, then flows into the upper cavity, and then enters the inner sleeve runner of the double-layer sleeve structure at the steam generator side through the outlet nozzle of the hanging basket to enter the steam generator; the coolant after heat exchange of the steam generator flows back to the main pump through the flow channels of the outer sleeve on the side of the steam generator, the outer ring cavity of the ring cavity structure and the outer sleeve on the side of the pump.
3. The reactor body structure of claim 2, wherein the ring cavity structure is fixed inside the pressure vessel by means of pinning or welding, and the ring cavity structure and the inner tube form a sealing fit by means of a mechanical connection shank combined with a sealing element.
4. The reactor body structure according to claim 3, wherein the hanging basket is provided with an opening corresponding to the outlet connection pipe of the pressure vessel, the opening is communicated with the inner pipe of the double-layer sleeve structure at the steam generator side, and the inner pipe and the annular cavity structure realize sealing at the opening.
5. The reactor body structure according to any one of claims 1 to 4, wherein the pressure vessel has a support shoulder, the upper internals include a guide tube support plate located at the top of the gondola, the flange of the gondola and the flange of the guide tube support plate are in turn superposed on the support shoulder of the pressure vessel and located above the annular chamber structure; through holes are formed in the corresponding positions of the hanging basket flange and the guide pipe support plate flange, and a spray pipe structure is installed in the through holes and communicated with the inner annular cavity; when coolant from a main pump enters the pressure vessel through the inner sleeve, a part of flow enters the interior of the upper end socket of the pressure vessel through the nozzle structure at the flange of the hanging basket and the flange of the support plate of the guide pipe, flows downwards to the upper cavity of the reactor, and flows out of the reactor through the outlet of the hanging basket.
6. The reactor body structure of claim 5, wherein a safety injection nozzle is arranged near the double-layer sleeve of the pressure vessel, a hole is formed at a corresponding position of the annular cavity structure, a through pipe structure is arranged to directly penetrate through the annular cavity structure to be matched and sealed with the safety injection nozzle, and in the event of core loss of coolant, the safety injection system is directly injected into the core through the safety injection nozzle, the inner straight pipe structure and the inner cavity of the annular cavity structure to prevent the core from melting.
7. The reactor body structure as claimed in claim 6, wherein the control rod driving mechanism is provided with a rod dropping auxiliary assembly to ensure that the rod can be dropped smoothly under the working conditions of swinging, tilting and the like in the marine environment, and the rod dropping time requirement is met.
8. The reactor body structure of claim 7 wherein said control rod drive mechanism is provided with a rollover lock to ensure that the control rod assembly does not withdraw out of the core in the event of a marine rollover.
9. The reactor body structure of claim 8 wherein said instrumentation assembly employs an integrated detector assembly to simultaneously measure core neutron fluence rate and core exit temperature, reducing the number of detectors.
10. The reactor body structure of claim 9 wherein said in-stack instrumentation components are collectively brought out from the top of the stack in groups.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110136849A (en) * | 2019-05-17 | 2019-08-16 | 中广核研究院有限公司 | A kind of reactor body construction of the nuclear steam supply system with double-layer sleeve structure |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110136849A (en) * | 2019-05-17 | 2019-08-16 | 中广核研究院有限公司 | A kind of reactor body construction of the nuclear steam supply system with double-layer sleeve structure |
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