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
- Publication number
- 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
- Authority
- CN
- China
- Prior art keywords
- deep
- reactor
- well
- normal pressure
- fuel
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- 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
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
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
This utility model relates to nuclear reactor field, and in particularly relating to a kind of deep-well, low-temperature atmosphere-pressure is for thermonuclear reaction
Heap.
Background technology
Deep-wall type normal pressure supplying heat nuclear reactor is a kind of low-temperature heat supply reactor, and this reactor is operated in relatively low
At a temperature of, the heat energy that nuclear fission produces is directly fed low temperature user, its simple in construction, build easily,
But need higher safety and reliability.Design the most both at home and abroad with the low-temperature nuclear heat supplying pile built is
Utilize swimmer's pool, hydrostatic pressure improve the temperature of core exit water, thus reach to improve the mesh of supply water temperature
's.
Pressurized-water reactor nuclear power plant primary Ioops heat transfer system refers to reactor core combustion in the pressure vessel in containment vessel
Material fission heat, the coolant heating that high pressure main pump is pumped into 327 DEG C, 15.5MPa, flow into steam generation
Device Secondary Circuit of PWR is intake heating evaporation become high temperature and high pressure steam, drive Turbo-generator Set send out
Electricity.Cooled coolant passes back into reactor core and absorbs nuclear heat, continues this technique and nuclear energy is converted into electric energy.
Reactor core, pressure vessel and Steam Generator U pipe, the main pump between it, main leg constitute presurized water reactor
Primary Ioops.Requirement is nuclear safety one-level that nuclear power station is the highest, its each material, manufacture equipment, technique, reality
Test the highest with detection requirement, be to require most stringent of forward position and high-end technology equipment the most in the world.
Currently the sodium fast reactor in research and development belongs to normal pressure with MSR nuclear power station, high temperature pool type reactor is to react in four generations
Heap, all suffers from enormous expenditure the difficult journey of very long research and development.
Low-temperature atmosphere-pressure district heating atomic power plant requires close with city central heating and low temperature multiple-effect distillation sea water desalting technology
Cut and agree with, meet especially administer haze, the security reliability that reduces carbon emission policy requirements is high, cost is low and
Good economy performance, is widely used, new nuclear power source technology that potential market is huge, is above the nuclear safety of forth generation
Technical equipment, necessarily by governments at all levels' support increasing with each side, quickly will see: more coming
The most place, low-temperature atmosphere-pressure well formula district heating atomic power plant occurs for heat supply the soonest, desalinization, for sky
Call cold water, industrial heat etc..
Along with manufacturing power " made in China 2025 " strategy implementation, well formula core heat supply process is upgraded with multiple
System matches function can more, application is wider, brings new great development.
Existing technical problem: it is to carry out nuclear fission release nuclear energy under high pressure and high temperature condition, though through 50
R & D design for many years, test, build, the development that runs and continuous advancement, around reactor core, containment,
Pressure vessel arranges increasing safety curtain, and the probability in its safe heap year is the most on the low side, domestic as numerous
CPR1000, secondary adding be all secondary half grade of nuclear power station；U.S. AP1000, France EPR and China of China
Dragon No. one: mainly increase residual heat of nuclear core passive discharge system, for three generations's nuclear power station, all there is no demonstration reactor.
Pool reactor, the power that will soon reach capacity when water flows through nucleus (3 arrive 5mv),
So if these water the most directly rise to reactor face, may result in test and excess radiation occurs
Problem.We are it is of course possible to attempt solving these difficult problems by corresponding solution.For example, it is possible to
When the water of swimming pool flows through nucleus, allow it pass through clarifier-tank facility simultaneously, and use resin ion to exchange
Process technique.Very unfortunate, greatly exceed routine owing to adopting the swimming-pool water amount of radiation produced in this way
Standard, it is impossible to processed by resin bed completely.People are also it is proposed that cross and use heat above pool surface
The scheme of water layer, oil reservoir or alcohol layer, or lay plexiglas under water at one or two meter, but these sides
Method inefficient or influence whether the accessibility of nucleus, therefore, has substantially completely exited swimming
Reactor applications market, pond.
The substantial amounts of spentnuclear fuel that nuclear power station draws off at present, all leaves in preservation pond, locates after sending after waiting
The disintegration of reason factory processes.These irradiated fuel assemblies the most do not use the ceiling value of burnup, do not give full play to
The potentiality of the further higher burnup of fuel assembly (are prior art existing problems？) it is not prior art
Problem, but have the power of nuclear power plant reactor and service condition to be determined.Nuclear power station is in High Temperature High Pressure
Under the conditions of, it is electric energy by the thermal transition that nuclear fission is produced.Require that reactor fuel assemblies has bigger
Power density, can be only achieved predetermined power；When power density reduce can not meet require time, become weary
Fuel.And the principle of low temperature heap is that nuclear energy is directly converted into heat energy, power is far below nuclear power station, exists simultaneously
Running under low-temperature atmosphere-pressure, therefore the reactor core density requirements for reactor is relatively low so that the spentnuclear fuel of nuclear power station
Meet low temperature heap power density requirements, thus can be further with, higher burnup.
Utility model content
For solving problem above, the utility model proposes a kind of deep-wall type normal pressure supplying heat nuclear reactor, it is adopted
The technical scheme taken is: a kind of deep-wall type normal pressure supplying heat nuclear reactor, including deep-well, the heap that is placed in bottom
Core, control rod, CRDM, also include safe pool, n attenuation cylinder, n inertia water
Case, residual heat of nuclear core discharge system and removable well lid, and described attenuation cylinder is arranged in the surrounding of reactor core, institute
State attenuation cylinder to be connected with inertia water tank, n >=2；Wherein,
The sidewall of described deep-well and bottom include inner side lining rustless steel wall, the concrete of outside lining carbon steel wall, institute
State safe pool and be arranged on the middle and upper part of deep-well, in described deep-well, be full of water；
Described safe pool includes spentnuclear fuel pond, fuel scratch pool and tank, and described spentnuclear fuel pond, fuel are temporary
Deposit pond and tank and deep-well reactor is connected to form big volumetric water system；
Described reactor core is equipped with the mixed nucleus fuel of fresh fuel and spentnuclear fuel；
Described residual heat of nuclear core discharges system waste heat in passive discharge deep-well, including being arranged on deep-well
The plate type heat exchanger in portion and be arranged on deep-well air above cooling tower, described plate type heat exchanger cools down with air
Plate air cooler in tower is connected；
Described removable well lid is arranged on deep-well top, is used for preventing flying object from colliding.
Further, the fuel combination in described heap, its fresh fuel with spentnuclear fuel mixing ratio is: 1:9--6:4.
Further, the perimeter region of described reactor core arranges the Simulation Core being made up of spentnuclear fuel.
Further, described spentnuclear fuel used or spentnuclear fuel of foreign nucleus reactor in being described reactor core.
Further, described mobile well lid is controlled to open and close by the turned crane of aboveground side.
Further, described control rod has many, and from below or top can be inserted in reactor core every control rod,
Described CRDM controls the up and down motion of every control rod respectively, is used for carrying out power adjustments or stopping
Heap.
Further, described attenuation cylinder includes multi-layer porous metallic plate, makes flow rate of hot water reduce also
Stream, extend flowing time and make flowing water radioactivity significantly decay.
Further, internal diameter 8 12m of described deep-well, deep 10 150m, wall thickness 0.5 2.1m, thickness
The end 1 4m.
Further, serving as a contrast rustless steel wall inside described deep-well is 0.3 0.8mm, described outside lining carbon steel wall
It is 5 15mm.
Further, described safe pool volume is 1000m3—1900m3。
The beneficial effects of the utility model are: under deep-well coolant water body natural pressure (normal pressure): have
The lowest operating pressure, the requirement of heat supply low temperature is greatly lowered the running temperature of reactor, and nuclear fission discharges
Recirculated water is heated to 98 DEG C (if in 150 meters of depth of waters, the highest temperature near reactor core by 78 DEG C by nuclear energy
Degree can be to 200 DEG C), the safety allowance of reactor is greatly improved, this atmospheric low-temperature deep-wall type reactor
There is no the systems such as pressure vessel, containment and peace note, be safety and the structure utilizing nuclear energy to meet heat supply needs
Simple reactor.Deep-well is connected with safe pool big volume water body, and very effective shielding is ensured radioactivity
In maximum natural and man-made calamities, physical security, includes that the armamentarium of passive discharge residual heat of nuclear core system all lost efficacy,
And under the conditions of can not intervening, remain to maintain 90 days core heap safety.
Accompanying drawing explanation
Fig. 1 is the structural representation of this utility model a kind of deep-wall type normal pressure supplying heat nuclear reactor.
Description of reference numerals: 1-deep-well, 2-reactor core, 3-control rod, 4-CRDM, 5-radiate
Decay cylinder, 6-inertia water tank, 7-may move well lid, 8-spentnuclear fuel pond, 9-fuel scratch pool, 10-
Tank, 11-plate type heat exchanger, 12-air cooling compressor.
Detailed description of the invention
Face combines the structure of accompanying drawing deep-wall type a kind of to this utility model normal pressure supplying heat nuclear reactor and does further
Describe: this embodiment is merely to illustrate this utility model rather than limits scope of the present utility model, ability
Field technique personnel all fall within the application claims to the amendment of the various equivalent form of values of the present utility model
Limited range.
As it is shown in figure 1, a kind of deep-wall type normal pressure supplying heat nuclear reactor, including deep-well 1, it is placed in bottom
Reactor core 2, control rod 3, CRDM 4, also include safe pool, n attenuation cylinder 5, n
Individual inertia water tank 6, residual heat of nuclear core discharge system and removable well lid 7, and described attenuation cylinder 5 is arranged in
The surrounding of reactor core 2, described attenuation cylinder 5 is connected with inertia water tank 6, n >=2；Wherein,
The sidewall of described deep-well and bottom include inner side lining rustless steel wall, the concrete of outside lining carbon steel wall, institute
State safe pool and be arranged on the middle and upper part of deep-well, in described deep-well, be full of water；
Described safe pool includes spentnuclear fuel pond 8, fuel scratch pool 9 and tank 10, described spentnuclear fuel pond 8,
Fuel scratch pool 9 and tank 10 and deep-well reactor are connected to form big volumetric water system；Spentnuclear fuel pond 8
And between fuel scratch pool 9, it is provided with dividing plate, it is provided with current bottom dividing plate and opens one's mouth；
Described reactor core 2 is equipped with the mixed nucleus fuel of fresh fuel and spentnuclear fuel；
Described residual heat of nuclear core discharges system waste heat in passive discharge deep-well, including being arranged on deep-well
The plate type heat exchanger 11 in portion and be arranged on deep-well air above cooling tower 12, described plate type heat exchanger is with empty
Plate air cooler in air cooling tower is connected；
Described removable well lid 7 is arranged on deep-well top, is used for preventing flying object from colliding.
Fuel combination in described heap 2, its fresh fuel with spentnuclear fuel mixing ratio is: 1:9--6:4；Reactor core 2
Perimeter region the Simulation Core that is made up of spentnuclear fuel is set；The upper surface of reactor core 2 is away from described deep-well 1 mouthful
3-6m。
Described spentnuclear fuel is used in described reactor core or the spentnuclear fuel of foreign nucleus reactor.
Deep-well 1 top is provided with removable well lid 7, is provided with two tracks in the outside of deep 1 top planes, can
Be respectively arranged with 2 rollers outside mobile both sides, well lid 7 bottom, can electronic, manually removable well lid 7 be removed with
Close, thick 1 2m of described removable well lid；
Being provided with two cranes (for illustrating in figure) in the main building of deep-well 1 top, the high overhead traveling crane in position is to hang
Fill, dismantle other equipment use, one accurate crane is set on removable well lid 7 top, be used for moving and hang down
Straight loading, unloading fuel and spentnuclear fuel.
Described control rod 3 has many, and from below or top can be inserted in reactor core 2 every control rod, described control
Rod drive mechanism 4 processed controls the up and down motion of every control rod respectively, is used for carrying out power adjustments or shutdown.
Described attenuation cylinder 5 is connected with reactor core 2 and inertia water tank 6 by rustless steel pipeline, attenuation
The structure of cylinder 5: by the sector drum of aluminium alloy plate inside and outside moderate soak layer, internal copper coin bundle with holes is constituted,
Make flow rate of hot water reduce and stream, extending flowing time and make flowing water radioactivity significantly decay；Inertia water tank 6
It is connected with heat-exchanging loop.
The inside diameter ranges of described deep-well 1 is 8---12m, deep 10---150m, wall thickness 0.5 2.1m, the thick end
1-4m。
Serving as a contrast rustless steel wall thickness inside deep-well is 0.3-0.8mm, and described outside lining carbon steel wall thickness is 5-15mm.
Described safe pool volume is 1000m3 1800m3, it is connected to form big volume water system with deep-well reactor
System.
At the bottom of fuel scratch pool 9 and pond, Simulation Core, fuel screen work are for fuel and spentnuclear fuel transhipment, exchange cloth
Put.
Spentnuclear fuel pond 8 systemic-function: the spentnuclear fuel of storage in-migration, cooling and purifying lasting to spentnuclear fuel water,
Spread out of the decay heat of spentnuclear fuel to ultimate heat sink such as air or earth's surface Large Copacity water body Ru Jiang, river, lake, sea.
Fill the tank 10 of water for for moisturizings such as spentnuclear fuel ponds.
During operation, the water as coolant flows through the fuel bundle of fission from reactor core 2 container bottom, from 78 DEG C
Being heated to 98 DEG C, the attenuation cylinder 5 separately flowing into 6 loops reduces flow velocity, postpones the delivery time
After water-borne radioactivity is greatly lowered, the hot side of plate type heat exchanger 11 that flows in corresponding 6 machine rooms release heat,
Heat cold survey secondary circuit water to spread out of, drop to 78 DEG C flowed back in deep-well 1 water by water pump, valve and return pipe,
Flow downward bottom entrance reactor core 2, so circulate and fission heat is constantly incoming secondary circuit by heat exchanger
Heat-exchange system.
During operation the water in inertia water tank 6 because of pressure descending water potential drop low, when shutdown particularly accident is promptly stopped
During heap water pump full cut-off, primary Ioops Shuitu so runs out of steam, and the water level in inertia water tank 6 rises, and strengthens reactor core
2 instantaneous deliveries, improve reactor core 2 safety.
Seat of honour heating plant reactor core loads preferred person in 90% fresh fuel, presurized water reactor spentnuclear fuel and accounts for for fuel
10%；When the first operation heat supply phase terminates cold-refueling: the spentnuclear fuel of a relatively high by detecting uranium enrichment
In the fuel screen work of the outer annular space that cloth is placed in reactor core, relatively low spentnuclear fuel cloth be placed on the screen work bottom deep-well
On；Add fresh fuel and lay corresponding station；It is obtained in that
1) 10% spentnuclear fuel continues to release fission heat；
2) be placed on outer shroud has been the fuel of spentnuclear fuel by presurized water reactor: continue to release fission heat；
3) the decay heat heating primary Ioops backwater of the spentnuclear fuel bottom deep-well it is placed on: decay heat become and have
Effect heat, and reduce spentnuclear fuel pond cooling power.
When the LOKA major accident of cut dehydration occur in the main pipeline in loop, pump, valve and heat exchanger,
Closing the valves such as corresponding stop valve, the water that discharge accident flows out overhauls.Reactor core 2 and other loop systems
System continues to run with heat supply；
And when nuclear power plant reactor occurs LOKA accident: all emergency shut-downs, take the emergency measures such as spray
Afterwards, overhaul.
Deep-wall type heat reactor described in the utility model, cold-refueling of annual needs, change wherein
The spentnuclear fuel of 1/6 reactor core amount.The spentnuclear fuel changed is being placed on the working area screen work storage of shaft bottom reactor core periphery
After 1 year, move to spentnuclear fuel processing means.For hankering in during this period, a loop is heated in spentnuclear fuel decay heat
The backwater of coolant, decay heat becomes effective heat.When needs cold-refueling draws off substantial amounts of spentnuclear fuel, essence
Spentnuclear fuel is removed by close crane from the reactor core 2 being placed in bottom, is stacked at the spentnuclear fuel layout being positioned at bottom
District, the top deep-well sidewall in spentnuclear fuel layout district arranges annular plate, and annular plate can gather heat effectively
Amount, the efficiency of the effectively heat of spentnuclear fuel output maximizes.
Meanwhile, described reactor is under deep-well coolant water body natural pressure (normal pressure): have the lowest fortune
Row pressure, the requirement of heat supply low temperature is greatly lowered the running temperature of reactor, and nuclear fission release nuclear energy will follow
Ring water is heated to 98 DEG C by 78 DEG C, and (if 150 meters of depth of waters, the maximum temperature near reactor core can arrive
200 DEG C), the safety allowance of reactor is greatly improved, this atmospheric low-temperature deep-wall type reactor is not pressed
The systems such as power shell, containment and peace note, are safety and the simple in construction utilizing nuclear energy to meet heat supply needs
Reactor.Deep-well is connected with safe pool big volume water body, and very effective shielding is ensured radioactive substance peace
Entirely, 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 the core heap safety of 90 days.
Claims (10)
1. a deep-wall type normal pressure supplying heat nuclear reactor, including deep-well (1), be placed in the reactor core of bottom (2), control
Rod processed (3), CRDM (4), be characterised by, also include safe pool, n attenuation cylinder (5),
N inertia water tank (6), residual heat of nuclear core discharge system and removable well lid (7), (5) described attenuation cylinder is arranged
In reactor core surrounding (2), (6) (5) described attenuation cylinder be connected with inertia water tank, n >=2；Wherein,
The sidewall of described deep-well and bottom include inner side lining rustless steel wall, the concrete of outside lining carbon steel wall, institute
State safe pool and be arranged on the middle and upper part of deep-well, in described deep-well, be full of water；
Described safe pool include spentnuclear fuel pond (8), fuel scratch pool (9) with tank (10), described spentnuclear fuel pond (8),
(10) (9) fuel scratch pool be connected to form big volumetric water system with tank with the deep-well of placing response heap；
Described reactor core is (2) equipped with the mixed nucleus fuel of fresh fuel and spentnuclear fuel；
Described residual heat of nuclear core discharges system waste heat in passive discharge deep-well, including being arranged on deep-well
(12) (11) the plate type heat exchanger in portion and be arranged on deep-well air above cooling tower, described plate type heat exchanger and air
Plate air cooler in cooling tower is connected；
(7) described removable well lid is arranged on deep-well top, is used for preventing flying object from colliding.
Deep-wall type normal pressure supplying heat nuclear reactor the most according to claim 1, it is characterised in that described heap
Core (2) in fuel combination, its fresh fuel with spentnuclear fuel mixing ratio is: 1:9--6:4.
Deep-wall type normal pressure supplying heat nuclear reactor the most according to claim 1 and 2, it is characterised in that institute
State reactor core perimeter region (2) and the Simulation Core being made up of spentnuclear fuel is set.
4. according to the deep-wall type normal pressure supplying heat nuclear reactor described in claim 1,2 or 3, it is characterised in that
Described spentnuclear fuel is used in described reactor core or the spentnuclear fuel of foreign nucleus reactor.
Deep-wall type normal pressure supplying heat nuclear reactor the most according to claim 1, it is characterised in that described can
(7) mobile well lid is controlled to open and close by the turned crane of aboveground side.
Deep-wall type normal pressure supplying heat nuclear reactor the most according to claim 1, it is characterised in that described control
(3) rod processed has many, every control rod from below or top can be inserted into reactor core (2) in, described control rod drives machine
Structure controls the up and down motion of every control rod the most respectively, is used for carrying out power adjustments or shutdown.
7. according to claim 1 deep-wall type normal pressure supplying heat nuclear reactor, it is characterised in that described radiation declines
Subtract cylinder and (5) include multi-layer porous metallic plate, make flow rate of hot water reduce and stream, extend flowing time and make flowing water
Radioactivity significantly decays.
Deep-wall type normal pressure supplying heat nuclear reactor the most according to claim 1, it is characterised in that describedly
Lower deep-well internal diameter 8 12m (1), deep 10 150m, wall thickness 0.5 2.1m, the thick end 1 4m.
Deep-wall type normal pressure supplying heat nuclear reactor the most according to claim 1, it is characterised in that in described
Side lining rustless steel wall is 0.3 0.8mm, and described outside lining carbon steel wall is 5 15mm.
Deep-wall type normal pressure supplying heat nuclear reactor the most according to claim 1, it is characterised in that described
Safe pool volume is 1000m3—1900m3。
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520965485.8U CN205810388U (en) | 2015-11-27 | 2015-11-27 | A kind of deep-wall type normal pressure supplying heat nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520965485.8U CN205810388U (en) | 2015-11-27 | 2015-11-27 | A kind of deep-wall type normal pressure supplying heat nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN205810388U true CN205810388U (en) | 2016-12-14 |
Family
ID=58143874
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201520965485.8U Active CN205810388U (en) | 2015-11-27 | 2015-11-27 | A kind of deep-wall type normal pressure supplying heat nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN205810388U (en) |
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 |
-
2015
- 2015-11-27 CN CN201520965485.8U patent/CN205810388U/en active Active
Cited By (6)
| 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 |
| 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 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN205810388U (en) | A kind of deep-wall type normal pressure supplying heat nuclear reactor | |
| CN101154472B (en) | Integrated low-temperature nuclear heat supplying pile | |
| CA2869561C (en) | Molten salt nuclear reactor | |
| CN109461506B (en) | Swimming pool type regional low-temperature heat supply stack | |
| CN105374408A (en) | Deep well type atmospheric pressure heat supply nuclear reactor | |
| CN104409109A (en) | Ultrahigh specific power thermal neutron thorium breeder reactor apparatus and method for nuclear fuel propagation | |
| CN105118534B (en) | Passive Spent Fuel Pool cooling and water charging system | |
| CN105590659B (en) | A kind of Residual heat removal ventilating system of nuclear power station dry storage spentnuclear fuel | |
| CN113990535B (en) | Integrated molten salt reactor heat exchanger and passive waste heat discharging system thereof | |
| WO2019184932A1 (en) | Underground neutron-energy power station | |
| Hannerz | Towards intrinsically safe light-water reactors | |
| CN106816181A (en) | A kind of cladding systems of fusion-fission reaction heap | |
| CN206601953U (en) | Cooling system outside a kind of passive pressure vessel | |
| CN106205747B (en) | Pool heat reactor and heat | |
| CN1316506C (en) | Deep water tank nuclear heat supply reactor adopting waste fuel of nuclear power station | |
| CN209216589U (en) | A kind of swimming pool formula region low temperature heating reactor | |
| CN206833929U (en) | A kind of cladding systems of fusion-fission reaction heap | |
| CN103366834A (en) | Thermal neutron high-speed multiplication system and multiplication method for production of nuclear fuel from thorium | |
| CN105575449A (en) | Deep-well normal-pressure nuclear heating system | |
| CN217008664U (en) | Nuclear energy heat supply reactor arrangement structure of shared reactor factory building | |
| JPH10319169A (en) | Helium cooled fast breeder reactor | |
| CN205388908U (en) | Ordinary pressure heat transfer system of deep well formula reactor | |
| CN108511091A (en) | A kind of pipe tube type pressurized water reactor system | |
| CN205541975U (en) | Deep well formula ordinary pressure nuclear heating system | |
| CN204303361U (en) | A kind of accident afterheat for large-scale pool type natrium cold fast reactor asymmetric arrangement discharges system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right |
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. |