CN107195334B - Accelerator driven subcritical gas cooled reactor - Google Patents
Accelerator driven subcritical gas cooled reactor Download PDFInfo
- Publication number
- CN107195334B CN107195334B CN201710428993.6A CN201710428993A CN107195334B CN 107195334 B CN107195334 B CN 107195334B CN 201710428993 A CN201710428993 A CN 201710428993A CN 107195334 B CN107195334 B CN 107195334B
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- reactor core
- pressure shell
- reactor
- heavy metal
- metal target
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
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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
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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
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
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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 invention provides an accelerator driven subcritical gas-cooled reactor, which comprises a pressure shell, wherein a supporting plate is arranged in the pressure shell, a cavity in the pressure shell is divided into an upper cavity and a lower cavity by the supporting plate, a reactor core is arranged on the upper side of the supporting plate in the upper cavity, a gap is reserved between the reactor core and the pressure shell, a gas outlet chamber is arranged in the lower cavity below the reactor core, the lower cavity outside the gas outlet chamber is a gas inlet chamber, a hot gas guide pipe comprising an inner cylinder and an outer cylinder is arranged on the side wall of the pressure shell of the lower cavity, the inner cylinder communicates the gas outlet chamber with the outside of the pressure shell, and a gap between the outer cylinder and the inner cylinder communicates the gas inlet chamber with the outside of the pressure shell; the support plate in the air outlet chamber is provided with a through hole, the through hole is used for communicating the reactor core with the air outlet chamber, the support plate between the reactor core and the inner wall of the pressure shell is provided with a through hole, the through hole is used for communicating the air inlet chamber with the upper chamber, and the lower end of the heavy metal target penetrating piece stretches into the upper chamber and sequentially penetrates through the reactor core, the air outlet chamber and the air inlet chamber and then penetrates out of the pressure shell. The invention has simple structure and strong practicability.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor equipment, and particularly relates to an accelerator-driven subcritical gas-cooled reactor.
Background
Nuclear energy is a mother of irreplaceable energy in the future, and has great efficacy in production, and along with the development of society, the conventional nuclear energy technology in the prior art cannot meet the diversified demands of society. There is a continuing need to develop and design new nuclear reactors to meet the needs of social diversification.
Disclosure of Invention
In view of the above, the present invention is directed to an accelerator driven subcritical gas cooled reactor for providing a nuclear reactor with a novel architecture.
In order to achieve the above purpose, the technical scheme of the invention is realized as follows:
the utility model provides an accelerator drive subcritical gas cooled reactor, including the pressure shell, the inside backup pad that sets up of pressure shell, the backup pad is divided into upper chamber and lower cavity with the cavity inside the pressure shell, the upside of the backup pad in the upper chamber is provided with the reactor core, leave the clearance between reactor core and the pressure shell, be provided with the air outlet chamber in the lower cavity below the reactor core, the lower cavity outside the air outlet chamber is the inlet chamber, the air outlet chamber is mutually independent with the inlet chamber, the lateral wall of the pressure shell of lower cavity is provided with the steam pipe, the steam pipe includes inner tube and urceolus, be provided with the space between urceolus and the inner tube, the inner tube will go out the outside intercommunication of air chamber and pressure shell, the space between urceolus and the inner tube will inlet chamber and the outside intercommunication of pressure shell;
the support plate in the air outlet chamber is provided with a through hole, the through hole is used for communicating the reactor core with the air outlet chamber, the support plate between the reactor core and the inner wall of the pressure shell is provided with a through hole, the through hole is used for communicating the air inlet chamber with the upper chamber, and the lower end of the heavy metal target penetrating piece stretches into the upper chamber and sequentially penetrates through the reactor core, the air outlet chamber and the air inlet chamber and then penetrates out of the pressure shell.
Further, the heavy metal target penetration is concentric with the core.
Further, the reactor core which is close to the heavy metal target penetrating piece and surrounds the heavy metal target penetrating piece is a fast neutron reaction area, the reactor core at the periphery of the fast neutron reaction area is a thermal neutron reaction area, the reactor core at the periphery of the thermal neutron reaction area is a power adjusting area, and the reactor core at the periphery of the power adjusting area is a reflecting layer.
Furthermore, the fast neutron reaction zone is filled with spent fuel or fissionable fuel, and the thermal neutron reaction zone is filled with U-235 fissionable material.
Further, 7-11 layers are arranged on the reactor core from top to bottom, and the uppermost layer and the lowermost layer are respectively reflecting layers.
Further, a control rod for controlling the power of the reactor is arranged at the upper end of the pressure shell, and the lower end of the control rod extends into a power adjusting area of the reactor core.
Further, an absorption ball channel for throwing the absorption balls is arranged at the upper end of the pressure shell, and the lower end of the absorption ball channel extends into a power adjusting area of the reactor core.
Further, a heavy metal target is arranged in the heavy metal target penetrating piece in the reactor core, and a coil for accelerating protons is arranged in the heavy metal target penetrating piece above the heavy metal target.
Further, a heavy metal target is arranged in the heavy metal target penetrating piece near the lower end of the reactor core, and the heavy metal target is made of lead-bismuth eutectic materials.
Further, the pressure shell comprises an upper sealing head and a lower sealing head, the upper sealing head and the lower sealing head are fixedly connected through a flange, a reactor core, an air outlet chamber and an air inlet chamber are respectively arranged in the lower sealing head, and an absorption ball channel and a control rod are respectively arranged on the upper sealing head.
Compared with the prior art, the accelerator-driven subcritical gas-cooled reactor has the following advantages:
(1) The invention has simple structure and strong practicability, can be used for generating power, treating spent fuel, producing easily-cracked nuclear raw materials such as U235 and the like, adopts subcritical form reaction, and has inherent safety and reliability;
(2) The invention is provided with two shutdown systems, and has higher safety and reliability;
(3) The heavy metal target penetration piece is internally provided with the coil for accelerating the protons, so that the speed of the protons can be greatly improved, and more neutrons are generated by bombarding the target.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention and do not constitute an undue limitation on the invention. In the drawings:
FIG. 1 is a schematic diagram of an embodiment of the present invention;
fig. 2 is a schematic structural view of a core according to an embodiment of the present invention.
Reference numerals illustrate:
1. a pressure shell; 101. an upper end enclosure; 102. a lower end enclosure; 2. a support plate; 3. a heavy metal target penetration; 31. a heavy metal target; 4. a hot gas conduit; 401. an inner cylinder; 402. an outer cylinder; 5. a core; 51. a fast neutron reaction zone; 52. a thermal neutron reaction zone; 53. a power adjustment zone; 54. a reflective layer; 6. a control rod; 7. an absorbent ball channel; a. an upper chamber; b. a gas outlet chamber; c. an intake chamber.
Detailed Description
It should be noted that, without conflict, the embodiments of the present invention and features of the embodiments may be combined with each other.
In the description of the invention, it should be understood that the terms "center," "longitudinal," "transverse," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like indicate orientations or positional relationships that are based on the orientation or positional relationships shown in the drawings, merely to facilitate describing the invention and simplify the description, and do not indicate or imply that the device or element being referred to must have a particular orientation, be configured and operate in a particular orientation, and therefore should not be construed as limiting the invention. Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first", "a second", etc. may explicitly or implicitly include one or more such feature. In the description of the invention, unless otherwise indicated, the meaning of "a plurality" is two or more.
In the description of the invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the creation of the present invention can be understood by those of ordinary skill in the art in a specific case.
The invention will be described in detail below with reference to the drawings in connection with embodiments.
As shown in fig. 1 and 2, an accelerator-driven subcritical gas cooled reactor comprises a pressure shell 1, wherein a support plate 2 is arranged in the pressure shell 1, and the support plate 2 divides a cavity in the pressure shell 1 into an upper cavity a and a lower cavity. A core 5 is provided on the upper side of the support plate 2 in the upper chamber a, and a gap for coolant to flow is left between the core 5 and the pressure shell 1. An air outlet chamber b is arranged in a lower chamber right below the reactor core 5, the lower chamber except the air outlet chamber b is an air inlet chamber c, and the air outlet chamber b and the air inlet chamber c are separated by a partition plate and are mutually independent. The side wall of the pressure shell 1 of the lower chamber is provided with a hot gas duct 4, which hot gas duct 4 is connected to the side edge of the pressure shell 1 by means of bolts. The hot air conduit 4 comprises an inner cylinder 401 and an outer cylinder 402 which are coaxial, and the outer cylinder 402 is fixedly connected on the pressure shell 1 through bolts. A space for coolant to flow is provided between the outer tube 402 and the inner tube 401, the inner tube 401 communicates the gas outlet chamber b with the outside of the pressure shell 1, and a space between the outer tube 402 and the inner tube 401 communicates the gas inlet chamber c with the outside of the pressure shell 1. The support plate 2 in the air outlet chamber b is provided with a through hole 202, the through hole 202 communicates the reactor core 5 with the air outlet chamber b, the support plate 2 between the reactor core 5 and the inner wall of the pressure shell 1 is provided with the through hole 202, and the through hole 202 communicates the air inlet chamber c with the upper chamber a. The pressure shell 1 is provided in a vertically penetrating structure for mounting the heavy metal target penetration 3. The lower end of the heavy metal target penetrating member 3 extends into the upper chamber a and sequentially passes through the reactor core 5, the outlet chamber b and the inlet chamber c and then passes out of the pressure shell 1. The heavy metal target penetrating piece 3, the reactor core 5, the gas outlet chamber b and the pressure shell 1 are coaxial.
The reactor core 5, which is close to the heavy metal target penetration piece 3 and surrounds the heavy metal target penetration piece 3, is a fast neutron reaction zone 51, only 6 hexagonal tunnels around the heavy metal target 31 are provided with fast neutron reaction zones 51, and the fast neutron reaction zones 51 are filled with spent fuel or other fissionable fuel. The reactor core 5 at the periphery of the fast neutron reaction area 51 is a thermal neutron reaction area 52, and U-235 fissionable materials are arranged in the thermal neutron reaction area 52. The core 5 around the thermal neutron reaction region 52 is a power adjustment region 53, and the core 5 around the power adjustment region 53 is a reflection layer 54. The fast neutron reaction area 51 and the thermal neutron reaction area 52 respectively generate fast neutron reaction and thermal neutron reaction, the power adjusting area 53 can be inserted into the control rod 6 and the absorption ball to adjust the power of the reactor, and the reflecting layer 54 is used for shielding neutrons and plays a role in heat insulation of internal and external coolants. The core 5 is provided with 7 to 11 layers from top to bottom, and the uppermost layer and the lowermost layer are respectively a reflecting layer 54 for preventing neutrons from radiating out of the pressure shell 1.
The upper end of the pressure shell 1 is provided with control rods 6 for controlling the reactor power, and the lower ends of the control rods 6 extend into a power adjustment zone 53 of the core 5. The upper end of the pressure shell 1 is also provided with an absorption ball channel 7 for controlling the reactor power, and the lower end of the absorption ball channel 7 extends into a power adjusting zone 53 of the reactor core 5. The absorption ball channel 7 forms a second shutdown system of the reactor, and can release the absorption balls to the reactor core 5 under the condition that the control rod 6 fails, and the purpose of reactor shutdown is achieved after neutrons are absorbed by the absorption balls. The control rods 6 and the absorbent ball channels 7 are arranged at even intervals. The circumferential side of the support plate 2 is provided with an annular step, which can increase the welding area and improve the welding strength.
The heavy metal target penetrating piece 3 inside the reactor core 5 is internally provided with a heavy metal target 31, the heavy metal target 31 is arranged in the heavy metal target penetrating piece 3 near the lower end of the reactor core 5, and the heavy metal target 31 is a heavy metal target 31 made of lead-bismuth eutectic materials. A coil for accelerating protons is arranged in the heavy metal target penetrating member 3 above the heavy metal target 31, and the coil can generate a magnetic field for accelerating protons.
The pressure shell 1 comprises an upper end enclosure 101 and a lower end enclosure 102, wherein the upper end enclosure 101 and the lower end enclosure 102 are fixedly connected through flanges, a reactor core 5, an air outlet chamber b and an air inlet chamber c are respectively arranged in the lower end enclosure 102, an absorption ball channel 7 and a control rod 6 are respectively arranged on the upper end enclosure 101, and a necessary measuring sensor is further arranged on the upper end enclosure 101.
The working principle of the invention is as follows:
(1) The heavy metal target penetrating piece 3 comprises a coil, a magnetic field generated by the coil accelerates protons moving in the orbit of the heavy metal target penetrating piece 3, the protons impact on a heavy metal target 31 formed by lead-bismuth eutectic after obtaining enough energy, and neutrons generated by the heavy metal target 31 radiate to the periphery.
(2) After being released from the heavy metal target 31, neutrons firstly reach a fast neutron reaction area 51, the fast neutron reaction area 51 is filled with spent fuel or other fissionable fuel, the energy of the neutrons reaching the fast neutron reaction area is higher, and the spent fuel is excited to transmute or other fissionable fuel is caused to react; a part of neutrons with lower energy reach the thermal neutron reaction area 52, and the thermal neutron reaction area 52 is filled with materials with easy cracking such as U-235 and the like to trigger thermal neutrons in the area to react; neutrons reach the peripheral reflective layer 54 or the upper and lower reflective layers of the core 5 and are reflected to prevent reaching the outside, thereby maintaining a low radiation level outside the pressure shell 1.
(3) Helium is selected as a two-loop coolant in the invention, the reactor core 5 reacts, high-temperature helium is taken as the coolant to enter the air inlet chamber c from a gap between the outer cylinder 402 and the inner cylinder 401 of the hot gas conduit 4, the helium flows into the upper chamber a through the supporting plate 2, then enters the reactor core 5 from the upper part of the reactor core 5, cools the reactor core 5 from top to bottom, finally flows out from the inner cylinder 401 of the hot gas conduit 4 after entering the air outlet chamber b, and the cooling of the reactor is completed.
(4) The power adjustment of the reactor is realized through the control rods 6, the reactor adjusts the power of the reactor core 5 by controlling the length of the control rods 6 extending into the reactor core 5, and when the control rods 6 are completely inserted into the reactor core 5, the reactor stops running; when the control rod 6 fails, a second set of cooling system is adopted to flow the absorption balls from the absorption ball channel 7 into the reactor core 5, and the absorption balls absorb neutrons and then scram the reactor.
The invention relates to a nuclear energy system which takes spent fuel as fuel, and excites high-energy neutrons through accelerating proton bombardment of a target material to react with the spent fuel or other fissionable nuclear raw materials, thereby transmuting nuclear waste. The accelerator driven subcritical reactor is expected to be a very potential method for treating nuclear waste, and is also an effective means for producing fissionable nuclear raw materials. In addition, the reactor can also output certain power, and the dual purposes of nuclear waste treatment and power generation can be realized.
The above embodiments are merely preferred embodiments of the present invention and are not intended to limit the present invention, and any modifications, equivalent substitutions, improvements, etc. within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (8)
1. An accelerator driven subcritical gas cooled reactor, characterized by:
the device comprises a pressure shell (1), wherein a supporting plate (2) is arranged inside the pressure shell (1), a cavity inside the pressure shell (1) is divided into an upper cavity (a) and a lower cavity by the supporting plate (2), a reactor core (5) is arranged on the upper side of the supporting plate (2) in the upper cavity (a), a gap is reserved between the reactor core (5) and the pressure shell (1), an air outlet chamber (b) is arranged in the lower cavity below the reactor core (5), the lower cavity outside the air outlet chamber (b) is an air inlet chamber (c), the air outlet chamber (b) is independent of the air inlet chamber (c), a hot air duct (4) is arranged on the side wall of the pressure shell (1) of the lower cavity, the hot air duct (4) comprises an inner cylinder (401) and an outer cylinder (402), a gap is arranged between the outer cylinder (402) and the inner cylinder (401), and the inner cylinder (401) is used for communicating the air outlet chamber (b) with the outside of the pressure shell (1), and the air inlet chamber (c) is communicated with the outside of the pressure shell (1) by the gap between the outer cylinder (402) and the inner cylinder (401);
a through hole (202) is formed in the supporting plate (2) in the air outlet chamber (b), the through hole (202) is used for communicating the reactor core (5) with the air outlet chamber (b), the through hole (202) is formed in the supporting plate (2) between the reactor core (5) and the inner wall of the pressure shell (1), the through hole (202) is used for communicating the air inlet chamber (c) with the upper chamber (a), and the lower end of the heavy metal target penetrating piece (3) stretches into the upper chamber (a) and sequentially penetrates through the reactor core (5), the air outlet chamber (b) and the air inlet chamber (c) and then penetrates out of the pressure shell (1); an absorption ball channel (7) for throwing the absorption balls is arranged at the upper end of the pressure shell (1), and the lower end of the absorption ball channel (7) extends into a power adjusting area (53) of the reactor core (5); the upper end of the pressure shell (1) is provided with a control rod (6) for controlling the reactor power, and the lower end of the control rod (6) stretches into a power adjusting zone (53) of the reactor core (5).
2. The accelerator driven subcritical gas cooled reactor of claim 1, wherein:
the heavy metal target penetrating piece (3) is coaxial with the reactor core (5).
3. The accelerator driven subcritical gas cooled reactor of claim 1, wherein:
the reactor core (5) which is close to the heavy metal target penetrating piece (3) and surrounds the heavy metal target penetrating piece (3) is a fast neutron reaction region (51), the reactor core (5) at the periphery of the fast neutron reaction region (51) is a thermal neutron reaction region (52), the reactor core (5) at the periphery of the thermal neutron reaction region (52) is a power regulation region (53), and the reactor core (5) at the periphery of the power regulation region (53) is a reflecting layer (54).
4. The accelerator driven subcritical gas cooled reactor of claim 3, wherein:
spent fuel or fissionable fuel is arranged in the fast neutron reaction region (51), and U-235 fissionable material is arranged in the thermal neutron reaction region (52).
5. The accelerator driven subcritical gas cooled reactor of claim 1, wherein:
7-11 layers are arranged on the reactor core (5) from top to bottom, and the uppermost layer and the lowermost layer are respectively reflecting layers.
6. The accelerator driven subcritical gas cooled reactor of claim 1, wherein:
the heavy metal target penetrating piece (3) in the reactor core (5) is internally provided with a heavy metal target (31), and the heavy metal target penetrating piece (3) above the heavy metal target (31) is internally provided with a coil for accelerating protons.
7. The accelerator driven subcritical gas cooled reactor of claim 1, wherein:
a heavy metal target (31) is arranged in the heavy metal target penetrating piece (3) close to the lower end of the reactor core (5), and the heavy metal target (31) is made of lead-bismuth eutectic materials.
8. The accelerator driven subcritical gas cooled reactor of claim 1, wherein:
the pressure shell (1) comprises an upper end enclosure (101) and a lower end enclosure (102), wherein the upper end enclosure (101) and the lower end enclosure (102) are fixedly connected through a flange, a reactor core (5), an air outlet chamber (b) and an air inlet chamber (c) are respectively arranged in the lower end enclosure (102), and an absorption ball channel (7) and a control rod (6) are respectively arranged on the upper end enclosure (101).
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| CN201710428993.6A CN107195334B (en) | 2017-06-08 | 2017-06-08 | Accelerator driven subcritical gas cooled reactor |
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| CN201710428993.6A CN107195334B (en) | 2017-06-08 | 2017-06-08 | Accelerator driven subcritical gas cooled reactor |
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| CN107195334A CN107195334A (en) | 2017-09-22 |
| CN107195334B true CN107195334B (en) | 2023-08-01 |
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Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN106373621A (en) * | 2016-11-14 | 2017-02-01 | 清华大学天津高端装备研究院 | Reactor core structure of lead-bismuth reactor ADS |
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| DE3009390A1 (en) * | 1980-03-12 | 1981-09-17 | GHT Gesellschaft für Hochtemperaturreaktor-Technik mbH, 5060 Bergisch Gladbach | HIGH TEMPERATURE REACTOR |
| FR2631484B1 (en) * | 1988-05-13 | 1992-08-21 | Framatome Sa | NUCLEAR REACTOR WITH EMERGENCY COOLING WATER INJECTION DEVICE |
| CN1945751B (en) * | 2006-11-21 | 2010-05-12 | 中国原子能科学研究院 | Accelerator driven fast-thermally coupled subcritical reactor |
| JP2010276564A (en) * | 2009-06-01 | 2010-12-09 | Toshihisa Shirakawa | 920k superheated steam boiling water reactor |
| EP2471070A1 (en) * | 2009-08-28 | 2012-07-04 | Searete LLC | A nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
| HUE036705T2 (en) * | 2011-09-21 | 2018-07-30 | Armin Huke | Dual fluid reactor |
| CA2908737A1 (en) * | 2013-03-15 | 2014-12-24 | Sutherland Cook ELLWOOD | Accelerator-driven subcritical reactor system |
| CN104464842B (en) * | 2014-12-22 | 2017-02-22 | 中国科学院合肥物质科学研究院 | Accelerator driven lead bismuth cooling subcritical traveling wave reactor |
| CN105023621B (en) * | 2015-06-12 | 2017-11-10 | 陈安海 | The implementation and its nuclear reactor of fast heap-type coupling nuclear reaction |
| CN106531229B (en) * | 2016-12-29 | 2017-10-13 | 中国科学院合肥物质科学研究院 | A kind of multi-functional nuclear power system of Novel ring cavate |
| CN206833931U (en) * | 2017-06-08 | 2018-01-02 | 清华大学天津高端装备研究院 | A kind of Accelerator Driven Subcritical gas-cooled reactor |
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| CN106373621A (en) * | 2016-11-14 | 2017-02-01 | 清华大学天津高端装备研究院 | Reactor core structure of lead-bismuth reactor ADS |
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