CN111199806B - Heat pipe reactor supporting and shielding structure with emergency cooling function - Google Patents
Heat pipe reactor supporting and shielding structure with emergency cooling function Download PDFInfo
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- CN111199806B CN111199806B CN201911414623.2A CN201911414623A CN111199806B CN 111199806 B CN111199806 B CN 111199806B CN 201911414623 A CN201911414623 A CN 201911414623A CN 111199806 B CN111199806 B CN 111199806B
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- 238000001816 cooling Methods 0.000 title claims abstract description 69
- 239000002826 coolant Substances 0.000 claims abstract description 44
- 238000013016 damping Methods 0.000 claims description 4
- 238000009434 installation Methods 0.000 abstract description 4
- 238000004519 manufacturing process Methods 0.000 abstract description 3
- 238000004321 preservation Methods 0.000 description 5
- 239000002131 composite material Substances 0.000 description 4
- 238000010248 power generation Methods 0.000 description 4
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 229910052761 rare earth metal Inorganic materials 0.000 description 1
- 150000002910 rare earth metals Chemical class 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/02—Biological shielding ; Neutron or gamma shielding
- G21C11/028—Biological shielding ; Neutron or gamma shielding characterised by the form or by the material
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
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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
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Biomedical Technology (AREA)
- General Health & Medical Sciences (AREA)
- Molecular Biology (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of nuclear reactors, and particularly relates to a heat pipe reactor supporting and shielding structure with an emergency cooling function. The invention comprises two annular reactor supports, a shielding structure, an emergency coolant inlet structure and an emergency coolant outlet structure; each position of the two annular reactor supports corresponds to the upper plate and the lower plate of the reactor vessel, the outer diameter of each annular reactor support is connected with the shell, and the inner diameter of each annular reactor support is matched with the reactor vessel; the shielding structure comprises a lower shielding plate, a middle shielding cylinder and an upper shielding plate; the lower shielding plate is arranged on the lower surface of the lower reactor support, the middle shielding cylinder is arranged between the two annular reactor supports, and the upper shielding plate is arranged above the upper reactor support; the emergency coolant inlet structure is mounted above the upper shield plate, and the emergency coolant outlet structure is mounted below the lower shield plate. The invention has simple and reliable structure, easy manufacture and installation and capability of realizing emergency cooling for the heat pipe reactor.
Description
Technical Field
The invention belongs to the technical field of nuclear reactors, and particularly relates to a heat pipe reactor supporting and shielding structure with an emergency cooling function.
Background
The heat pipe reactor adopts heat pipes for heat conduction, has no system loop and high-power mechanical rotating equipment, has the technical characteristics of long service life or even whole service life without material change, high inherent safety, low noise, high power volume-weight ratio, simple and reliable system equipment and the like, realizes thermoelectric conversion by combining a plurality of advanced power generation technologies such as thermocouple power generation, thermoacoustic power generation, thermophotovoltaic power generation and the like, and can be widely applied to the fields of underwater space stations, land emergency disaster relief, island and reef power supply and seawater desalination, offshore energy exploitation, small-sized city power supply and heat supply and the like as energy supply options.
The reactor supporting and shielding structure is one of the key components of the heat pipe reactor, and has the functions of supporting the weight of the reactor body structure, bearing various external loads, shielding the radioactive leakage of the reactor to within the specified limit value and the like. Meanwhile, the heat preservation function and the shielding function of the reactor body are integrally implemented by considering the characteristics of the low-power heat pipe stack.
For the research of the heat pipe reactor, a large amount of research is carried out by related research units at home and abroad, but the public reports are mostly macroscopic reports, and the reactor supporting and shielding structure provided by the invention is not described in detail. The technical invention is different from the publicly reported structural arrangement form (figure 1), and compared with a frame reactor support and concrete shielding structure adopted by a commercial pressurized water reactor, the structural design, design function and operation mechanism are completely different, the structure not only can realize the heat preservation of the reactor structure and the shielding of the radioactivity generated by the reactor under the normal operation condition, but also can be used as an emergency cooling system to prevent the reactor from melting at high temperature under the accident condition. The invention has simple structure, high inherent safety and composite function, and is especially suitable for the simplified design of the heat pipe reactor structure. Compared with a common reactor supporting and shielding structure, the structure has the functions of heat preservation and emergency cooling under accidents of the reactor, not only simplifies the whole structure, but also is more beneficial to realizing the structural engineering of the whole reactor.
Disclosure of Invention
The technical problems solved by the invention are as follows:
the invention mainly aims at the requirements of a heat pipe reactor in various future application occasions, and provides a heat pipe reactor supporting and shielding structure with an emergency cooling function, which has the advantages of simple and reliable structure, easiness in manufacturing and installation and capability of being applied to the structural design of the heat pipe reactor.
The technical scheme adopted by the invention is as follows:
a heat pipe reactor supporting and shielding structure with an emergency cooling function comprises two annular reactor supporting, shielding structures, an emergency coolant inlet structure and an emergency coolant outlet structure; each position of the two annular reactor supports corresponds to the upper plate and the lower plate of the reactor vessel, the outer diameter of each annular reactor support is connected with the shell, and the inner diameter of each annular reactor support is matched with the reactor vessel; the shielding structure comprises a lower shielding plate, a middle shielding cylinder and an upper shielding plate; the lower shielding plate is arranged on the lower surface of the lower reactor support, the middle shielding cylinder is arranged between the two annular reactor supports, and the upper shielding plate is arranged above the upper reactor support; the emergency coolant inlet structure is mounted above the upper shield plate, and the emergency coolant outlet structure is mounted below the lower shield plate.
The lower reactor support is of a stepped ring structure, the annular step is used for supporting and positioning the reactor container, the step surface is provided with a plurality of emergency cooling holes, bolt mounting holes and pin holes, the emergency cooling holes are used for allowing emergency coolant to pass through, the bolt mounting holes are used for mounting bolts to enable the lower reactor support and the reactor container to be connected together, and the pin holes are used for the lower reactor support and the reactor container positioning.
The upper reactor support is of a circular ring structure, a plurality of emergency cooling holes are formed in the plane and used for communicating emergency coolant, and the inner ring is further provided with an elastic vibration damping structure which is used for supporting the reactor vessel, reducing external load transmitted to the reactor vessel and accommodating axial thermal expansion of the reactor vessel.
The lower shielding plate is of a circular plate-shaped structure, is provided with a plurality of emergency cooling holes for introducing emergency coolant and a plurality of step holes for installing a rotary drum driving mechanism, and is fixed on the lower reactor support through fasteners.
The middle shielding cylinder is of a cylindrical structure and is positioned between the lower reactor support and the upper reactor support, and the middle shielding cylinder is positioned and connected through a fastener.
The upper shielding plate is of a circular plate-shaped structure and is fixed on the upper reactor support through a fastener; the upper shielding plate is provided with a concave platform corresponding to one side of the reactor container, the depth of the annular step is the axial thermal expansion difference value of the reactor container when the reactor is in normal operation and when the reactor is installed at normal temperature, the middle area is also provided with a heat pipe hole corresponding to the arrangement of the heat pipe for the heat pipe to pass through, and the edge area is provided with emergency cooling holes with the same number and aperture corresponding to the emergency cooling holes on the upper reactor support.
The emergency coolant inlet structure is positioned above the upper shielding plate and is a ring pipe structure with a plurality of branch pipes; the branch pipe is connected with the inlet ring pipe and the upper shielding plate through structures such as threads, nuts, gaskets and the like; the emergency coolant outlet structure is consistent with the emergency coolant inlet structure in structural form, is arranged below the lower shielding plate, is of a ring pipe structure with a plurality of branch pipes and comprises an outlet main pipe, an outlet ring pipe and the branch pipes; the branch pipe is connected with the outlet ring pipe and the lower shielding plate through structures such as threads, nuts, gaskets and the like.
When an accident occurs, emergency coolant from an emergency cooling system enters a ring pipe of an emergency coolant inlet structure through an inlet main pipe, flows through emergency cooling holes of an upper shielding plate and emergency cooling holes of an upper reactor support in sequence after being distributed by a plurality of branch pipes, enters a ring cavity formed by a reactor container and a middle shielding barrel, cools the reactor, leads out heat of a reactor core, then flows out of the emergency cooling holes of a lower reactor support and the emergency cooling holes of a lower shielding plate in sequence, enters branch pipes of an emergency cooling outlet structure, is led into the emergency cooling system through an outlet main pipe after being collected to the ring pipe, and forms circulation.
The invention has the beneficial effects that:
the heat pipe reactor supporting and shielding structure disclosed by the invention is simple and reliable in structure and easy to manufacture and install, has the functions of supporting a reactor and shielding radioactivity in the prior art, is simultaneously designed to be made of a heat-insulating shielding composite material and have a heat-insulating function by adopting a ring cavity structure, reduces the number of independent heat-insulating layers, forms an emergency cooling channel for the heat pipe reactor by combining an emergency cooling inlet and outlet structure, and has the capability of realizing emergency cooling for the heat pipe reactor.
Drawings
In order to more clearly illustrate the embodiments of the present invention, the drawings, which are required to describe the embodiments of the present invention, will be briefly described below. It is obvious that the drawings in the following description are only some embodiments described in the present invention, and that other drawings can be derived from the following drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic illustration of a pressurized water reactor support and shielding configuration of the prior art;
FIG. 2 is a schematic illustration of the installation of the heat pipe reactor support and shield structure provided by the present invention;
FIG. 3 is a schematic view of a lower reactor support structure;
FIG. 4 is a schematic view of an upper reactor support structure;
FIG. 5 is a schematic view of a lower shield plate structure;
FIG. 6 is a schematic view of an upper shield plate structure;
FIG. 7 is a first schematic view of an emergency coolant inlet and outlet;
FIG. 8 is a schematic view of a second emergency coolant inlet/outlet structure;
in the figure: 1-reactor support, 2-shielding structure, 3-emergency coolant inlet structure, 4-emergency coolant outlet structure, 5-reactor container, 6-concrete support, 7-frame type reactor support, 8-reactor pressure container heat-insulating layer, 9-reactor pressure container, 11-lower reactor support, 111-emergency cooling hole, 112-bolt mounting hole, 113-annular step and 114-positioning pin hole; 12-upper reactor support, 121-emergency cooling hole, 122-elastic damping structure; 21-lower shield plate, 211-emergency cooling hole, 212-driving mechanism mounting hole, 213-annular step; 22-middle shielding cylinder; 23-upper shield plate, 231-emergency cooling hole, 232-heat pipe hole, 233-circular step; 31-inlet main pipe, 32-inlet ring pipe and 33-branch pipe; 41-outlet manifold, 42-outlet loop and 43-branch.
Detailed Description
The following provides a further detailed description of a support and shield structure for a heat pipe reactor with emergency cooling function according to the present invention with reference to the accompanying drawings and specific embodiments.
As shown in fig. 2: the invention provides a heat pipe reactor supporting and shielding structure with an emergency cooling function, which comprises two annular reactor supporting structures 1, a shielding structure 2, an emergency coolant inlet structure 3 and an emergency coolant outlet structure 4; each position of the two annular reactor supports 1 corresponds to the upper plate and the lower plate of the reactor vessel 5, the outer diameter is connected with the shell, the inner diameter is matched with the reactor vessel 5, and the structural form is not completely consistent; the shielding structure 2 comprises a lower shielding plate 21, a middle shielding cylinder 22 and an upper shielding plate 23; the lower shield plate 21 is installed on the lower surface of the lower reactor support 11, the middle shield cylinder 22 is installed between the two annular reactor supports 1, and the upper shield plate 23 is installed above the upper reactor support 12. The emergency coolant inlet arrangement 3 is mounted above the upper shield plate 23 and the emergency coolant outlet arrangement 4 is mounted below the lower shield plate 21.
As shown in fig. 3: the lower reactor support 11 is of a stepped circular ring structure, the annular step 113 is used for providing support and positioning for the reactor vessel 5, the step surface is provided with a plurality of emergency cooling holes 111, bolt mounting holes 112 and pin holes 114, the emergency cooling holes 111 are used for introducing emergency coolant, the bolt mounting holes 112 are used for mounting bolts to connect the lower reactor support 11 and the reactor vessel 5 together, and the pin holes 114 are used for positioning the lower reactor support 11 and the reactor vessel 5.
As shown in fig. 4: the upper reactor support 12 is a circular ring structure, the plane is provided with a plurality of emergency cooling holes 121 for communicating emergency coolant, and the inner ring is further provided with an elastic damping structure 122 for supporting the reactor vessel 5 and reducing external load transmitted to the reactor vessel 5, and accommodating thermal expansion of the reactor vessel 5 in the axial direction.
As shown in fig. 5: the lower shield plate 21 is a circular plate-shaped structure, and is provided with a plurality of emergency cooling holes 211 for passing emergency coolant and a plurality of stepped holes 212 for installing a rotary drum driving mechanism, and is fixed on the lower reactor support 11 by fasteners.
The middle shield canister 22 is a cylindrical structure, and is located between the lower reactor support 11 and the upper reactor support 12, and is positioned and connected by fasteners.
As shown in fig. 6: the upper shield plate 23 is a circular plate-shaped structure and is fixed to the upper reactor support by fasteners. The upper shield plate 23 has a concave platform corresponding to one side of the reactor vessel 5, the depth of the annular step 233 is the difference between the thermal expansion in the axial direction of the reactor vessel 5 during normal operation of the reactor and during normal temperature installation, the arrangement of the heat pipes corresponding to the middle region is further provided with heat pipe holes 232 for the heat pipes to pass through, and the edge region is provided with emergency cooling holes 231 with the same number and aperture corresponding to the emergency cooling holes 121 on the upper reactor support 12.
As shown in fig. 7 and 8: the emergency coolant inlet arrangement 3 is located above the upper shield plate 23 in a collar arrangement with a number of branch pipes 33. The branch pipe 33 connects the inlet collar 32 and the upper shield plate 23 by means of a screw, nut, washer, etc. An inlet manifold 31 is provided on the inlet collar 32 opposite the branch pipes 33 for connection to the emergency cooling system, the orientation being determined by the orientation of the emergency cooling system.
The emergency coolant outlet structure 4 has the same structural form as the emergency coolant inlet structure 3, is arranged below the lower shielding plate 21, is a ring pipe structure with a plurality of branch pipes, and consists of an outlet main pipe 41, an outlet ring pipe 42 and a branch pipe 43. The branch pipe 43 connects the outlet collar 42 and the lower shield plate 21 by means of a screw, a nut, a washer, or the like. An outlet manifold 41 is provided on the outlet ring pipe 42 opposite the branch pipe 43 for communication with the emergency cooling system, the orientation angle being determined by the orientation of the emergency cooling system.
The working principle of the invention is as follows: in case of an accident, the emergency coolant from the emergency cooling system enters the loop 32 of the emergency coolant inlet structure through the inlet manifold 31, flows through the emergency cooling holes 231 of the upper shield plate 23 and the emergency cooling holes 121 of the upper reactor support 12 in sequence after being distributed by the plurality of branch pipes 33, enters the annular cavity formed by the reactor vessel 5 and the middle shield cylinder 22 to cool the reactor, and discharges the core heat, and then flows out of the emergency cooling holes 111 of the lower reactor support 11 and the emergency cooling holes 211 of the lower shield plate 21 in sequence, enters the branch pipes 43 of the emergency cooling outlet structure 4, is collected in the loop 42, and then is introduced into the emergency cooling system through the outlet manifold 41 to form a circulation.
When the reactor normally operates, the inside of the reactor is kept static by closing the valves arranged at the outer sides of the inlet manifold 31 and the outlet manifold 41, so that the heat preservation effect of the reactor is achieved. The reactor shielding structure is made of composite materials with heat preservation and shielding functions, and the composite materials are generally rare earth-based materials.
Claims (8)
1. The utility model provides a take emergent cooling function's heat pipe reactor supporting and shielding structure which characterized in that: the system comprises two annular reactor supports (1), a shielding structure (2), an emergency coolant inlet structure (3) and an emergency coolant outlet structure (4); each position of the two annular reactor supports (1) corresponds to the upper plate and the lower plate of the reactor vessel (5), the outer diameter of each annular reactor support corresponds to the shell, and the inner diameter of each annular reactor support corresponds to the reactor vessel (5); the shielding structure (2) comprises a lower shielding plate (21), a middle shielding cylinder (22) and an upper shielding plate (23); the lower shielding plate (21) is arranged on the lower surface of the lower reactor support (11), the middle shielding cylinder (22) is arranged between the two annular reactor supports (1), and the upper shielding plate (23) is arranged above the upper reactor support (12); the emergency coolant inlet structure (3) is mounted above the upper shield plate (23) and the emergency coolant outlet structure (4) is mounted below the lower shield plate (21).
2. The heat pipe reactor support and shield structure with emergency cooling function of claim 1, wherein: the lower reactor support (11) is of a stepped ring structure, an annular step (113) is used for supporting and positioning a reactor container (5), a plurality of emergency cooling holes (111), bolt mounting holes (112) and pin holes (114) are formed in the step surface, the emergency cooling holes (111) are used for introducing emergency coolant, the bolt mounting holes (112) are used for mounting bolts to enable the lower reactor support (11) and the reactor container (5) to be connected together, and the pin holes (114) are used for positioning the lower reactor support (11) and the reactor container (5).
3. The heat pipe reactor support and shield structure with emergency cooling function of claim 1, wherein: the upper reactor support (12) is of a circular ring structure, a plurality of emergency cooling holes (121) are formed in the plane and used for communicating emergency coolant, and an elastic vibration damping structure (122) is further arranged on the inner ring and used for supporting the reactor vessel (5), reducing external load transmitted to the reactor vessel (5) and accommodating axial thermal expansion of the reactor vessel (5).
4. The heat pipe reactor support and shield structure with emergency cooling function of claim 1, wherein: the lower shielding plate (21) is of a circular plate-shaped structure, is provided with a plurality of emergency cooling holes (211) for introducing emergency coolant and a plurality of step holes (212) for installing a rotary drum driving mechanism, and is fixed on the lower reactor support (11) through fasteners.
5. The heat pipe reactor support and shield structure with emergency cooling function of claim 1, wherein: the middle shielding cylinder (22) is of a cylindrical structure and is positioned between the lower reactor support (11) and the upper reactor support (12) and is positioned and connected through a fastener.
6. The heat pipe reactor support and shield structure with emergency cooling function of claim 1, wherein: the upper shielding plate (23) is of a circular plate-shaped structure and is fixed on the upper reactor support through a fastener; one side of the upper shielding plate (23) corresponding to the reactor container (5) is provided with a concave platform, the depth of the concave platform is the axial thermal expansion difference value of the reactor container (5) when the reactor is in normal operation and is installed at normal temperature, the middle area is provided with a heat pipe hole (232) corresponding to the arrangement of the heat pipe for the heat pipe to pass through, and the edge area is provided with emergency cooling holes (231) with the same number and aperture corresponding to the emergency cooling holes (121) on the upper reactor support (12).
7. The heat pipe reactor support and shield structure with emergency cooling function of claim 1, wherein: the emergency coolant inlet structure (3) is positioned above the upper shielding plate (23) and is of a ring pipe structure with a plurality of branch pipes (33); the branch pipe (33) is connected with the inlet ring pipe (32) and the upper shielding plate (23) through a thread, a nut and a gasket structure; the emergency coolant outlet structure (4) is consistent with the emergency coolant inlet structure (3) in structural form, is arranged below the lower shielding plate (21), is a ring pipe structure with a plurality of branch pipes, and comprises an outlet main pipe (41), an outlet ring pipe (42) and branch pipes (43); the branch pipe (43) is connected with the outlet ring pipe (42) and the lower shielding plate (21) through a screw thread, a nut and a gasket structure.
8. The heat pipe reactor support and shield structure with emergency cooling function of any one of claims 1-7, wherein: when an accident occurs, emergency coolant from an emergency cooling system enters a ring pipe (32) of an emergency coolant inlet structure through an inlet main pipe (31), flows through emergency cooling holes (231) of an upper shielding plate (23) and emergency cooling holes (121) of an upper reactor support (12) in sequence after being distributed through a plurality of branch pipes (33), enters a ring cavity formed by a reactor container (5) and a middle shielding cylinder (22), cools a reactor, guides out heat of a reactor core, then flows out from emergency cooling holes (111) of a lower reactor support (11) and emergency cooling holes (211) of a lower shielding plate (21) in sequence, enters branch pipes (43) of an emergency cooling outlet structure (4), is collected to an outlet ring pipe (42), and then is guided to the emergency cooling system through an outlet main pipe (41) to form circulation.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201911414623.2A CN111199806B (en) | 2019-12-31 | 2019-12-31 | Heat pipe reactor supporting and shielding structure with emergency cooling function |
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|---|---|---|---|
| CN201911414623.2A CN111199806B (en) | 2019-12-31 | 2019-12-31 | Heat pipe reactor supporting and shielding structure with emergency cooling function |
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| CN111199806A CN111199806A (en) | 2020-05-26 |
| CN111199806B true CN111199806B (en) | 2022-04-19 |
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| CN113299411B (en) * | 2021-05-25 | 2022-03-01 | 中国核动力研究设计院 | Radiation shielding heat preservation device and design method and application thereof |
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| CN202650568U (en) * | 2012-06-08 | 2013-01-02 | 中国核动力研究设计院 | Comprehensive protection device for nuclear reactor container |
| CN103474103A (en) * | 2012-06-08 | 2013-12-25 | 中国核动力研究设计院 | Metal insulation device capable of achieving external cooling of reactor pressure vessel |
| CN203338768U (en) * | 2013-07-26 | 2013-12-11 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel protection device |
| CN104916333A (en) * | 2014-03-12 | 2015-09-16 | 上海核工程研究设计院 | Novel triple containment for coping with severe accidents |
| CN105280249A (en) * | 2015-09-16 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shield walling composite structure |
| CN106898390A (en) * | 2015-12-21 | 2017-06-27 | 中国核动力研究设计院 | A kind of reactor pressure vessel supporting structure with function of shielding |
| CN108010591A (en) * | 2017-12-18 | 2018-05-08 | 中广核研究院有限公司 | A kind of multifunctional pressure container reactor pit structure and reactor safety shell structure |
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