CN205810388U - A kind of deep-wall type normal pressure supplying heat nuclear reactor - Google Patents
A kind of deep-wall type normal pressure supplying heat nuclear reactor Download PDFInfo
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- CN205810388U CN205810388U CN201520965485.8U CN201520965485U CN205810388U CN 205810388 U CN205810388 U CN 205810388U CN 201520965485 U CN201520965485 U CN 201520965485U CN 205810388 U CN205810388 U CN 205810388U
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Classifications
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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
-
- 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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Abstract
The utility model proposes a kind of deep-wall type normal pressure supplying heat nuclear reactor, including being embedded in the deep-well of underground, being placed in the reactor core of bottom, control rod, CRDM, it is characterised by, also include that subsurface safety pond, attenuation box, inertia water tank, residual heat of nuclear core discharge system and removable well lid, described attenuation cylinder is connected with inertia water tank, is full of water in described Deep Underground.Deep-wall type normal pressure supplying heat nuclear reactor has the lowest operating pressure, the requirement of low-temperature heat supply is greatly lowered the running temperature of reactor, this underground atmospheric low-temperature deep-wall type reactor does not has pressure vessel, containment and the system such as peace note and off site emergency, is safety and the simplest nuclear reactor of structure utilizing nuclear energy to meet heat supply needs.Deep-well is connected with spentnuclear fuel pond big volume water body simultaneously, pure water is by the radioactivity of very effective shielding radioactive substance, ensure the safety of hot well periphery operator, include that the armamentarium of passive discharge residual heat of nuclear core system all lost efficacy in maximum natural and man-made calamities, and under the conditions of can not intervening, remain to maintain 90 days core heap safety.
Description
Technical Field
The utility model relates to a nuclear reactor field especially relates to a low temperature ordinary pressure heat supply nuclear reactor in deep well.
Background
The deep well type normal pressure heat supply nuclear reactor is a low temperature heat supply reactor, which works at a lower temperature and directly supplies the heat energy generated by nuclear fission to low temperature users, and has simple structure and easy construction, but needs higher safety and reliability. The low-temperature nuclear heat supply reactor designed and built at home and abroad at present utilizes a deep water pool to increase the temperature of water at the outlet of a reactor core by hydrostatic pressure, thereby achieving the purpose of increasing the water supply temperature.
The primary circuit heat transfer system of the pressurized water reactor nuclear power station is characterized in that fuel in a reactor core in a pressure shell in a containment vessel is heated, coolant pumped by a high-pressure main pump is heated to 327 ℃ and 15.5MPa, and the coolant flows into a steam generator to heat and evaporate secondary circuit inlet water of the pressurized water reactor nuclear power station into high-temperature high-pressure steam to drive a steam turbine generator unit to generate electricity. The cooled coolant is returned to the core to absorb nuclear heat energy, and the process continues to convert the nuclear energy to electrical energy.
The reactor core, the pressure shell, the U-shaped pipe of the steam generator, the main pump and the main pipe section between the U-shaped pipe of the steam generator form a primary circuit of the pressurized water reactor. The requirements are the highest nuclear safety level of a nuclear power station, the respective materials, manufacturing equipment, processes, experiments and monitoring requirements are the highest, and the nuclear power station is the most strict leading-edge and high-end technical equipment in the world nowadays.
The sodium fast reactor and the molten salt reactor nuclear power station which are researched and developed at present belong to a four-generation reactor which is a normal-pressure high-temperature pool type reactor, and face huge cost and long research and development difficulty courses.
The low-temperature normal-pressure nuclear heating plant is closely matched with the technical requirements of urban central heating and low-temperature multi-effect distillation seawater desalination, particularly meets the requirements of haze treatment and carbon emission reduction policies on high safety reliability, low manufacturing cost and good economical efficiency, is widely applied and has huge potential market, is a nuclear safety technical device higher than the fourth generation, is inevitably supported by governments at all levels and more in all aspects, and can be seen quickly: low-temperature normal-pressure well-type nuclear heating stations are used for heating, seawater desalination, cold water for air conditioners, industrial heat and the like in more and more places and more rapidly.
With the strategic implementation of the '2025 made by China' in the strong country of manufacture, the functions of the well-type nuclear heating technology upgrading and various system matching are more, the application is wider, and new and larger development is brought.
The existing technical problems are as follows: the nuclear fission is carried out under the conditions of high pressure and high temperature to release nuclear energy, although development and continuous progress of research, development, experiment, construction and operation are carried out for more than 50 years, more and more safety barriers are arranged around a reactor core, a containment vessel and a pressure shell, the probability of the safety reactor is still low, and domestic such as a plurality of CPR1000 and second-generation plus all are second-generation half-level nuclear power stations; american AP1000, french EPR and chinese hualong number one: the reactor core waste heat passive discharge system is mainly added, and is a third-generation nuclear power station without a demonstration reactor.
Swimming pool reactors reach the limit power (3 to 5mv) quickly as the water flows through the core area, which can lead to excessive radiation problems in the test if the water rises directly to the reactor surface again. We can of course try to solve these difficulties by a corresponding solution. For example, the water of the swimming pool may be passed through the purification tank facility while passing through the core area, and a treatment process of resin ion exchange may be employed. Unfortunately, this method does not completely treat the water in the resin bed because the radiation level of the water in the swimming pool is much higher than the conventional standard. Solutions have also been proposed to use hot water, oil or alcohol layers above the pool surface, or to lay plexiglas one or two meters under water, but these methods are inefficient or interfere with the accessibility of the core area, thus essentially completely exiting the pool reactor application market.
At present, a large amount of spent fuel discharged by a nuclear power station is stored in a storage pool and is sent to a post-treatment plant for disintegration treatment after waiting. None of these spent fuel assemblies uses the highest limit of burnup, and the potential of the fuel assemblies to further increase burnup (is one of the problems in the prior art. Nuclear power plants convert heat generated by nuclear fission into electrical energy under high temperature and pressure conditions. A greater power density is required for the reactor fuel assembly to achieve the predetermined power; when the power density reduction can not meet the requirement, the fuel becomes spent fuel. The principle of the low-temperature reactor is that nuclear energy is directly converted into heat energy, the power is far lower than that of the nuclear power station, and the low-temperature reactor operates at low temperature and normal pressure, so that the requirement on the density of a reactor core of the reactor is low, and spent fuel of the nuclear power station meets the requirement on the power density of the low-temperature reactor, so that the spent fuel can be further utilized, and the fuel consumption is deepened.
SUMMERY OF THE UTILITY MODEL
In order to solve the above problems, the utility model provides a deep-well formula ordinary pressure heat supply nuclear reactor, the technical scheme that it adopted is: a deep well type normal pressure heat supply nuclear reactor comprises a deep well, a reactor core arranged at the bottom of the well, a control rod driving mechanism, a safety pool, n radiation attenuation cylinders, n inertia water tanks, a reactor core waste heat discharge system and a movable well cover, wherein the radiation attenuation cylinders are arranged around the reactor core and are connected with the inertia water tanks, and n is more than or equal to 2; wherein,
The side wall and the bottom of the deep well comprise concrete with an inner stainless steel lining wall and an outer carbon steel lining wall, the safety pool is arranged at the middle upper part of the deep well, and the deep well is filled with water;
the safety pool comprises a spent fuel pool, a temporary fuel storage pool and a water storage pool, and the spent fuel pool, the temporary fuel storage pool and the water storage pool are connected with the deep well reactor to form a large-volume water system;
the reactor core is filled with mixed nuclear fuel of fresh fuel and spent fuel;
the reactor core waste heat discharge system is used for passively discharging waste heat in a deep well, and comprises a plate heat exchanger arranged at the upper part of the deep well and an air cooling tower arranged above the deep well, wherein the plate heat exchanger is connected with a plate air cooler in the air cooling tower;
the movable well cover is arranged at the top of the deep well and used for preventing the collision of flyers.
Further, the mixed fuel in the stack has a new fuel and spent fuel mixing ratio of: 1:9- -6:4.
Further, a simulated core made of spent fuel is provided in the outer peripheral region of the core.
Further, the spent fuel is spent fuel in the core or spent fuel of an exotic nuclear reactor.
Further, the moving well lid is controlled to open and close by a hoist above the well.
Further, the control rods are provided with a plurality of control rods, each control rod can be inserted into the reactor core from the lower part or the upper part, and the control rod driving mechanism respectively controls the up-and-down movement of each control rod for power regulation or reactor shutdown.
Furthermore, the radiation attenuation cylinder comprises a plurality of layers of porous metal plates, so that the flow velocity of hot water is reduced and the hot water flows around, and the flow time is prolonged, so that the radioactivity of the flowing water is greatly attenuated.
Furthermore, the deep well has an inner diameter of 8-12 m, a depth of 10-150 m, a wall thickness of 0.5-2.1 m and a thick bottom of 1-4 m.
Furthermore, the inner side of the deep well is lined with a stainless steel wall of 0.3-0.8 mm, and the outer side is lined with a carbon steel wall of 5-15 mm.
Further, the volume of the safety pool is 1000m3—1900m3。
The utility model has the advantages that: under the natural pressure (normal pressure) of deep well coolant water: the reactor has very low operation pressure, the operation temperature of the reactor is greatly reduced by the low temperature requirement of heat supply, the nuclear fission releases nuclear energy to heat circulating water from 78 ℃ to 98 ℃ (if the nuclear fission releases nuclear energy in a water depth of 150 meters, the highest temperature near the reactor core can reach 200 ℃), the safety allowance of the reactor is greatly improved, the normal-pressure low-temperature deep-well reactor has no systems such as a pressure shell, a containment vessel and safety injection, and the reactor is the safest and simple in structure reactor which can meet the heat supply requirement by using the nuclear energy. The deep well is connected with a large-volume water body of the safety pool, so that the safety of radioactive substances can be effectively shielded, all equipment including a passive reactor core waste heat discharging system is out of work in the largest natural disaster and accident, and the safety of the nuclear reactor can be maintained for 90 days under the condition that the intervention cannot be performed.
Drawings
Fig. 1 is a schematic structural diagram of a deep-well normal-pressure heat supply nuclear reactor of the present invention.
Description of reference numerals: the system comprises a deep well 1, a reactor core 2, control rods 3, control rod drive mechanisms 4, a radiation attenuation cylinder 5, an inertia water tank 6, a movable well cover 7, a spent fuel pool 8, a temporary fuel storage pool 9, a water storage pool 10, a plate heat exchanger 11 and an air cooling tower 12.
Detailed Description
The structure of the deep well type normal pressure heat supply nuclear reactor of the utility model is further described with the accompanying drawings: the examples are given solely for the purpose of illustration and are not intended to limit the scope of the invention, as modifications of various equivalent forms of the invention by those skilled in the art will fall within the scope of the invention as defined in the claims appended hereto.
As shown in fig. 1, a deep-well type normal-pressure heat supply nuclear reactor comprises a deep well 1, a reactor core 2 arranged at the bottom of the well, a control rod 3, a control rod driving mechanism 4, a safety pool, n radiation attenuation cylinders 5, n inertia water tanks 6, a reactor core waste heat discharge system and a movable well cover 7, wherein the radiation attenuation cylinders 5 are arranged around the reactor core 2, the radiation attenuation cylinders 5 are connected with the inertia water tanks 6, and n is more than or equal to 2; wherein,
The side wall and the bottom of the deep well comprise concrete with an inner stainless steel lining wall and an outer carbon steel lining wall, the safety pool is arranged at the middle upper part of the deep well, and the deep well is filled with water;
the safety pool comprises a spent fuel pool 8, a temporary fuel storage pool 9 and a water storage pool 10, wherein the spent fuel pool 8, the temporary fuel storage pool 9 and the water storage pool 10 are connected with the deep well reactor to form a large-volume water system; a clapboard is arranged between the spent fuel pool 8 and the temporary fuel pool 9, and the bottom of the clapboard is provided with a water flow port;
the reactor core 2 is filled with mixed nuclear fuel of fresh fuel and spent fuel;
the reactor core waste heat discharge system is used for passively discharging waste heat in a deep well, and comprises a plate heat exchanger 11 arranged at the upper part of the deep well and an air cooling tower 12 arranged above the deep well, wherein the plate heat exchanger is connected with a plate air cooler in the air cooling tower;
the movable well cover 7 is arranged on the top of the deep well and used for preventing the collision of flyers.
The mixed fuel in the stack 2 has the mixing ratio of the new fuel to the spent fuel as follows: 1:9- -6: 4; a simulated reactor core composed of spent fuel is arranged in the peripheral region of the reactor core 2; the upper surface of the reactor core 2 is 3-6m away from the deep well 1.
The spent fuel is spent fuel in the core or spent fuel of an exotic nuclear reactor.
The top of the deep well 1 is provided with a movable well lid 7, the outer side of the top plane of the deep well 1 is provided with two tracks, the outer parts of two sides of the lower part of the movable well lid 7 are respectively provided with 2 rollers, the movable well lid 7 can be moved away and closed electrically and manually, and the thickness of the movable well lid is 1-2 m;
two cranes (shown in the figure) are arranged in a main workshop at the upper part of the deep well 1, a high crown block is used for hoisting and disassembling other equipment, and a precision crane is arranged at the upper part of the movable well cover 7 and used for moving and vertically loading and unloading fuel and spent fuel.
The control rods 3 are provided with a plurality of control rods, each control rod can be inserted into the reactor core 2 from the lower part or the upper part, and the control rod driving mechanism 4 respectively controls the up-and-down movement of each control rod and is used for power regulation or reactor shutdown.
The radiation attenuation cylinder 5 is connected with the reactor core 2 and the inertia water tank 6 through a stainless steel pipeline, and the structure of the radiation attenuation cylinder 5 is as follows: the heat-insulating water heater consists of a fan-shaped cylinder of aluminum alloy plates inside and outside a middle heat-insulating layer and a copper plate bundle with holes inside, so that the flow speed of hot water is reduced and the hot water flows around, and the flowing time is prolonged, so that the flowing water radioactivity is greatly attenuated; the inertia water tank 6 is connected with the heat exchange loop.
The inner diameter range of the deep well 1 is 8-12 m, the depth is 10-150 m, the wall thickness is 0.5-2.1 m, and the thickness is 1-4 m.
The wall thickness of the stainless steel lining on the inner side of the deep well is 0.3-0.8mm, and the wall thickness of the carbon steel lining on the outer side is 5-15 mm.
The volume of the safety pool is 1000m 3-1800 m3And is connected with a deep well reactor to form a large-volume water system.
The temporary fuel storage pool 9, the simulated reactor core at the bottom of the pool and the fuel grillwork are used for transferring, exchanging and distributing fuel and spent fuel.
The spent fuel pool 8 has the system functions: storing the moved spent fuel, continuously cooling and purifying the water in the spent fuel pool, and transferring decay heat of the spent fuel to a final heat sink such as the atmosphere or surface large-capacity water bodies such as rivers, lakes and seas.
The water storage tank 10 filled with water is used to replenish water for spent fuel tanks and the like.
When in operation, water serving as a coolant flows through the fission fuel bundle from the bottom of the reactor core 2 container, is heated to 98 ℃ from 78 ℃, flows into the radiation attenuation cylinders 5 of the 6 loops respectively to reduce the flow rate and delay the outflow time to greatly reduce the water radioactivity, flows into the hot side of the plate heat exchanger 11 corresponding to the 6 machine rooms to release heat, heats and measures the secondary loop water to be transmitted, flows back to the deep well 1 water through the water pump, the valve and the water return pipe when the temperature is reduced to 78 ℃, flows downwards to enter the bottom of the reactor core 2, and then circularly flows to continuously transmit fission heat into the secondary loop heat exchange system through the heat exchanger.
When the water level in the inertia water tank 6 is reduced due to pressure drop during operation, and when the water pump is stopped completely during shutdown, particularly during emergency shutdown, a primary loop water suddenly loses power, the water level in the inertia water tank 6 rises, the instantaneous flow of the reactor core 2 is increased, and the safety of the reactor core 2 is improved.
The reactor core of the first heat supply station is filled with 90% of fresh fuel and the optimized one of the spent fuel of the pressurized water reactor, wherein the fuel accounts for 10%; when the shutdown and refueling are finished in the first operation heat supply period: the spent fuel with relatively high uranium enrichment degree is detected and placed in a fuel grid of an outer annular space in the core, and the low spent fuel is placed on a grid at the bottom of the deep well; then adding new fuel to distribute corresponding stations; this gives:
1) 10% of the spent fuel continues to emit cracked heat;
2) the press water stack placed on the outer ring is already spent fuel: continuously discharging cracking heat;
3) decay heat of the spent fuel placed at the bottom of the deep well heats primary loop return water: changing decay heat into useful heat and reducing spent fuel pool cooling power.
When major accident of LOKA of water loss of a breach appears in a main pipeline, a pump, a valve and a heat exchanger in the loop, the corresponding valves such as a stop valve are closed, and water flowing out of the discharged accident is overhauled. The reactor core 2 and other loop systems continue to operate for heat supply;
And when the nuclear power station reactor has a LOKA accident: emergency shutdown, spraying and other emergency measures are taken, and then overhaul is carried out.
The deep well type heat supply reactor needs to be shut down and reloaded once every year, and the spent fuel of 1/6 reactor core amount is replaced. The replaced spent fuel is stored in a temporary storage area grid frame arranged at the periphery of the reactor core at the bottom of the well for one year and then is moved to a spent fuel treatment device. During this period of heat supply, the spent fuel decay heat heats the return water of a loop coolant, and the decay heat becomes active heat. When a large amount of spent fuel needs to be discharged by stopping and reloading, the precise crane moves the spent fuel out of the reactor core 2 arranged at the bottom of the well and stacks the spent fuel in the spent fuel arrangement area at the bottom of the well, and the annular rib plates are arranged on the side wall of the deep well at the top of the spent fuel arrangement area and can effectively gather heat, so that the efficiency of the effective heat generated by the spent fuel is maximized.
Meanwhile, the reactor is under the natural pressure (normal pressure) of deep well coolant water: the reactor has very low operation pressure, the operation temperature of the reactor is greatly reduced by the low temperature requirement of heat supply, the nuclear fission releases nuclear energy to heat circulating water from 78 ℃ to 98 ℃ (if the nuclear fission releases nuclear energy in a water depth of 150 meters, the highest temperature near the reactor core can reach 200 ℃), the safety allowance of the reactor is greatly improved, the normal-pressure low-temperature deep-well reactor has no systems such as a pressure shell, a containment vessel and safety injection, and the reactor is the safest and simple in structure reactor which can meet the heat supply requirement by using the nuclear energy. The deep well is connected with a large-volume water body of the safety pool, so that the safety of radioactive substances can be effectively shielded, all equipment including a passive reactor core waste heat discharging system is out of work in the largest natural disaster and accident, and the safety of the nuclear reactor can be maintained for 90 days under the condition that the intervention cannot be performed.
Claims (10)
1. A deep-well normal-pressure heat supply nuclear reactor comprises a deep well, a reactor core arranged at the bottom of the well, a control rod driving mechanism and is characterized by further comprising a safety pool, n radiation attenuation cylinders, n inertia water tanks, a reactor core waste heat discharging system and a movable well cover, the radiation attenuation cylinders are arranged around the reactor core, the radiation attenuation cylinders are connected with the inertia water tanks, and n is more than or equal to 2; wherein,
the side wall and the bottom of the deep well comprise concrete with an inner stainless steel lining wall and an outer carbon steel lining wall, the safety pool is arranged at the middle upper part of the deep well, and the deep well is filled with water;
the safe pool comprises a spent fuel pool, a temporary fuel pool and a water storage pool, and the spent fuel pool, the temporary fuel pool and the water storage pool are connected with a deep well in which a reactor is placed to form a large-volume water system;
the mixed nuclear fuel of new fuel and spent fuel is loaded in the reactor core;
the reactor core waste heat discharge system is used for passively discharging waste heat in a deep well, and comprises a plate heat exchanger arranged at the upper part of the deep well and an air cooling tower pump arranged above the deep well, wherein the plate heat exchanger is connected with a plate air cooler in the air cooling tower;
The movable well cover is mounted on the top of the deep well and used for preventing collision of flyers.
2. The deep-well normal-pressure heat supply nuclear reactor according to claim 1, characterized in that the mixed fuel in the core II is the mixed fuel of new fuel and spent fuel, and the mixing ratio of the new fuel and the spent fuel is as follows: 1:9- -6:4.
3. The deep well normal pressure heat supply nuclear reactor of claim 1 or 2, wherein the periphery of the core II is provided with a simulated core made of spent fuel.
4. The deep well atmospheric pressure thermal nuclear reactor of claim 1, 2 or 3, wherein said spent fuel is spent fuel in said core or is foreign nuclear reactor spent fuel.
5. Deep-well atmospheric pressure heating nuclear reactor according to claim 1, characterized in that said movable manhole cover is controlled to be opened and closed by a crane above the well.
6. The deep-well normal-pressure heat supply nuclear reactor as claimed in claim 1, wherein the number of the control rods is three, each control rod can be inserted into the secondary core from below or above, and the control rod driving mechanisms control the up-and-down movement of each control rod respectively for power regulation or shutdown.
7. The deep well normal pressure thermal nuclear reactor of claim 1, wherein the radiation attenuating cylinder comprises a plurality of layers of porous metal plates, so that the flow velocity of hot water is reduced and the hot water flows around, and the flow time is prolonged, so that the radioactivity of the flowing water is greatly attenuated.
8. The deep-well normal-pressure heat supply nuclear reactor according to claim 1, characterized in that the deep underground well has an inner diameter of 8-12 m, a depth of 10-150 m, a wall thickness of 0.5-2.1 m, and a bottom thickness of 1-4 m.
9. A deep well atmospheric pressure thermal nuclear reactor as claimed in claim 1, wherein said inner stainless steel lined wall is 0.3-0.8 mm and said outer carbon lined steel wall is 5-15 mm.
10. Deep well atmospheric pressure thermal nuclear reactor according to claim 1, characterized in that said safety pool has a volume of 1000m3—1900m3。
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| CN201520965485.8U CN205810388U (en) | 2015-11-27 | 2015-11-27 | A kind of deep-wall type normal pressure supplying heat nuclear reactor |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105374408A (en) * | 2015-11-27 | 2016-03-02 | 田力 | Deep well type atmospheric pressure heat supply nuclear reactor |
| CN106898400A (en) * | 2017-03-27 | 2017-06-27 | 中核核电运行管理有限公司 | The remote region thermal energy supply system of large commercial nuclear energy mesohigh steam and method |
| CN109378089A (en) * | 2018-11-12 | 2019-02-22 | 中国原子能科学研究院 | A kind of in-pile component for swimming pool formula low temperature heating reactor power expansion |
| CN109473194A (en) * | 2018-11-12 | 2019-03-15 | 中国原子能科学研究院 | A kind of decaying cylinder for Deep Pool Low Temperature Heating Reactor |
| CN109545416A (en) * | 2018-12-29 | 2019-03-29 | 中国原子能科学研究院 | A kind of decaying cylinder for Deep Pool Low Temperature Heating Reactor |
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2015
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| CN105374408A (en) * | 2015-11-27 | 2016-03-02 | 田力 | Deep well type atmospheric pressure heat supply nuclear reactor |
| CN106898400A (en) * | 2017-03-27 | 2017-06-27 | 中核核电运行管理有限公司 | The remote region thermal energy supply system of large commercial nuclear energy mesohigh steam and method |
| CN109378089A (en) * | 2018-11-12 | 2019-02-22 | 中国原子能科学研究院 | A kind of in-pile component for swimming pool formula low temperature heating reactor power expansion |
| CN109473194A (en) * | 2018-11-12 | 2019-03-15 | 中国原子能科学研究院 | A kind of decaying cylinder for Deep Pool Low Temperature Heating Reactor |
| CN109473194B (en) * | 2018-11-12 | 2024-05-14 | 中国原子能科学研究院 | Attenuation tube for deep water tank type low-temperature heat supply stack |
| CN109545416A (en) * | 2018-12-29 | 2019-03-29 | 中国原子能科学研究院 | A kind of decaying cylinder for Deep Pool Low Temperature Heating Reactor |
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Effective date of registration: 20171205 Address after: 100085 A, No. 9, Third Street, Shanghai Haidian District, Beijing, 9 layer A1003-105 Patentee after: Kai Xin Xin nuclear (Beijing) Energy Technology Co., Ltd. Address before: 100193, Beijing, Haidian District, Zhongguancun northeast Beijing Software Park Incubator Building 2, block 2140-099, room B Patentee before: X-NUCLEAR (BEIJING) ENERGY TECH. CO., LTD. |