CN107146641A - The method of nuclear power system and control nuclear power system - Google Patents
The method of nuclear power system and control nuclear power system Download PDFInfo
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- CN107146641A CN107146641A CN201710329665.0A CN201710329665A CN107146641A CN 107146641 A CN107146641 A CN 107146641A CN 201710329665 A CN201710329665 A CN 201710329665A CN 107146641 A CN107146641 A CN 107146641A
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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
- G21C7/00—Control of nuclear reaction
- G21C7/34—Control of nuclear reaction by utilisation of a primary neutron source
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The embodiment provides a kind of nuclear power system and a kind of method of control nuclear power system, nuclear power system includes：Burner subsystem, burner subsystem includes the first reactor and neutron-producing target, the neutron produced by neutron-producing target makes the first reactor carry out nuclear reaction under subcritical state, and after the expiration of the predetermined period of time, the first reactor carries out nuclear reaction under critical conditions；And post-process subsystem for the fuel reproduction of core weary material processing.The method of control nuclear power system includes：The neutron produced by neutron-producing target makes the first reactor carry out nuclear reaction under subcritical state；And after the expiration of the predetermined period of time, the first reactor carries out nuclear reaction under critical conditions.Thus nuclear fuel utilization rate can at least be improved.
Description
Technical field
Embodiments of the invention are related to a kind of nuclear power system and a kind of method of control nuclear power system.
Background technology
At present, reactor is mainly water cooling thermal-neutron reactor, neutron pile using it is disposable by or U-Pu (uranium-plutonium) it is multiple
Nuclear fuel cycle mode.But it is low to there is nuclear fuel utilization rate, core weary material toxicity, post processing financial cost and core production peace
The problem of full blast is nearly high.
The content of the invention
The purpose of embodiments of the invention is to provide a kind of nuclear power system and a kind of method of control nuclear power system, thus extremely
Nuclear fuel utilization rate can be improved less.
The embodiment provides a kind of nuclear power system, the nuclear power system includes：First reactor and neutron-producing target, lead to
Crossing the neutron of neutron-producing target generation makes the first reactor carry out nuclear reaction under subcritical state, and is passing through predetermined time period
Afterwards, the first reactor carries out nuclear reaction under critical conditions.
Embodiments in accordance with the present invention, described nuclear power system also includes：Second reactor, in being produced by neutron-producing target
Son makes the second reactor carry out nuclear reaction under subcritical state, and after the expiration of the predetermined period of time, the second reactor exists
Nuclear reaction is carried out under critical condition.
Embodiments in accordance with the present invention, described nuclear power system also includes：Proton precessional magnetometer, the proton precessional magnetometer produces matter
Beamlet, and the proton beam incident neutron target produced by proton precessional magnetometer, produce neutron.
Embodiments in accordance with the present invention, the strength range for the proton beam that proton precessional magnetometer is produced is 800MeV~1500MeV.
Embodiments in accordance with the present invention, the flux for the neutron that neutron-producing target is produced is 1E+18n/s~3E+18n/s.
Embodiments in accordance with the present invention, neutron-producing target includes ceramic particle, and the ceramic particle can bear 10MW~30MW lines
Power.
Embodiments in accordance with the present invention, the particle diameter of ceramic particle is in millimeter magnitude
Under embodiments in accordance with the present invention, at least one in subcritical state and critical condition, the first reactor
The thermal power of reactor core is 600MW~2000MW.
Embodiments in accordance with the present invention, described nuclear power system also includes：Solid particle, by the use of the solid particle as cold
But medium is cooled down to the first reactor, under at least one in subcritical state and critical condition, and the cooling media exists
The temperature of the outlet of first reactor is 650~900 DEG C.
Embodiments in accordance with the present invention, described nuclear power system also includes：For locating after the fuel reproduction of core weary material processing
Manage subsystem.
Embodiments in accordance with the present invention, the nuclear power system is nuclear reactor system.
The embodiment provides a kind of method for controlling nuclear power system, the method for control nuclear power system includes：It is logical
Crossing the neutron of neutron-producing target generation makes the first reactor carry out nuclear reaction under subcritical state；And passing through predetermined time period
Afterwards, the first reactor carries out nuclear reaction under critical conditions.
Embodiments in accordance with the present invention, the method for described control nuclear power system also includes：In being produced by neutron-producing target
Son makes the second reactor carry out nuclear reaction under subcritical state.
Embodiments in accordance with the present invention, the method for described control nuclear power system also includes：Passing through predetermined time period
Afterwards, the second reactor carries out nuclear reaction under critical conditions.
Embodiments in accordance with the present invention, the method for described control nuclear power system also includes：Produced using proton precessional magnetometer
Proton beam；And the proton beam incident neutron target produced by proton precessional magnetometer, produce neutron.
Embodiments in accordance with the present invention, the strength range for the proton beam that proton precessional magnetometer is produced is 800MeV~1500MeV.
Embodiments in accordance with the present invention, the flux for the neutron that neutron-producing target is produced is 1E+18n/s~3E+18n/s.
Embodiments in accordance with the present invention, neutron-producing target includes ceramic particle, and the ceramic particle can bear 10MW~30MW lines
Power.
Embodiments in accordance with the present invention, the particle diameter of ceramic particle is in millimeter magnitude.
Under embodiments in accordance with the present invention, at least one in subcritical state and critical condition, the first reactor
The thermal power of reactor core is 600MW~2000MW.
Embodiments in accordance with the present invention, the method for described control nuclear power system also includes：By the use of solid particle as cold
But medium is cooled down to the first reactor, under at least one in subcritical state and critical condition, and the cooling media exists
The temperature of the outlet of first reactor is 650~900 DEG C.
Embodiments in accordance with the present invention, the nuclear power system is nuclear reactor system.
According to an embodiment of the invention nuclear power system and control nuclear power system method, can at least improve nuclear fuel makes
With rate.
Brief description of the drawings
Fig. 1 is the nuclear power system overall schematic of the Accelerator driven of the embodiment of the present invention；
Fig. 2 is burner subsystem schematic diagram in the nuclear power system of the Accelerator driven of the embodiment of the present invention；And
Fig. 3 is fuel reproduction post processing subsystem schematic diagram in the nuclear power system of the Accelerator driven of the embodiment of the present invention.
Embodiment
Below in conjunction with the accompanying drawings and embodiment the present invention will be further described.
Referring to Fig. 1 to 2, nuclear power system is controlled according to an embodiment of the invention, and (for example nuclear reactor system (for example burns
Device subsystem 101)) method include：The neutron produced by neutron-producing target 3 makes the first reactor (such as burner 2) face secondary
Nuclear reaction is carried out under boundary's state；And after section is asked when predetermined, the first reactor (such as burner 2) is in critical condition
Lower carry out nuclear reaction.This method can also include：The neutron produced by neutron-producing target 3 makes the second reactor, and (for example another fires
Burner 2) nuclear reaction is carried out under subcritical state, after the expiration of the predetermined period of time, (for example another burns the second reactor
Device 2) nuclear reaction is carried out under critical conditions.This method can also include：Proton beam is produced using proton precessional magnetometer 1；And it is logical
The proton beam incident neutron target 3 of the generation of proton precessional magnetometer 1 is crossed, neutron is produced.For example, with reference to Fig. 1 to 2, according to the reality of the present invention
Applying the nuclear power system (such as nuclear reactor system (such as burner subsystem 101)) of example includes：First reactor (for example burns
Device 2) and by neutron-producing target 3, the neutron produced by neutron-producing target 3 makes the first reactor (such as burner 2) in subcritical state
Lower progress nuclear reaction and after the expiration of the predetermined period of time, the first reactor (such as burner 2) is carried out under critical conditions
Nuclear reaction.The nuclear power system can also include：Second reactor (such as another burner 2), in being produced by neutron-producing target 3
Son makes the second reactor (such as another burner 2) carry out nuclear reaction under subcritical state, is passing through predetermined time period
Afterwards, the second reactor (such as another burner 2) carries out nuclear reaction under critical conditions.The nuclear power system can also include：
Proton precessional magnetometer 1, the proton precessional magnetometer 1 produces proton beam and the proton beam incident neutron target produced by proton precessional magnetometer 1
3, produce neutron.
According to the example of the present invention, this method is also carried out using solid particle as cooling media to the first reactor
Under cooling, at least one in subcritical state and critical condition, temperature of the cooling media in the outlet of the first reactor
For 650~900 DEG C.For example, nuclear power system also includes solid particle, reacted by the use of the solid particle as cooling media first
Heap is cooled down, under at least one in subcritical state and critical condition, and the cooling media is in the outlet of the first reactor
Temperature be 650~900 DEG C.
Nuclear power system according to an embodiment of the invention is specifically described with reference to example.
As shown in figure 1, the nuclear power system of the Accelerator driven of the embodiment of the present invention includes：Burner subsystem 101 and combustion
Material regeneration post processing subsystem 102.
As illustrated in fig. 1 and 2, burner subsystem 101 includes：At least one proton precessional magnetometer 1, such as superconduction straight line high current
Proton precessional magnetometer 1 and at least one burner 2.In order to obtain higher economy, it is extended to by many superconduction straight line high currents
Proton precessional magnetometer 1 drives the accelerator redundant mode of many burners 2.
Superconduction straight line high current proton precessional magnetometer 1 is the building block of burner subsystem 101, and its main function is for producing
Raw high current, high-power proton beam.In embodiments of the invention accelerator produce proton beam strength range for 800MeV~
1500MeV.Bombard the generation high flux neutron of Spallation target 3 (about 1E+18n/s~3E+18n/s) to remain anti-by proton beam
Chain reaction lasting in heap 4 is answered, so as to reach the purpose of production capacity and transmuting nuke rubbish.
Burner 2 includes neutron-producing target 3 (such as high power Spallation target 3), (preferably high temperature is fast for modular reactor 4
Heap), target material after-treatment device 5, target heat-exchange system 6, reactor coolant after-treatment device 7 and reactor heat-exchange system 8 etc.
Device.Wherein, high power Spallation target 3 uses the windowless target design configuration of particle stream, target body overall diameter 30-50cm；Modularization
Reactor 4 heat transferring medium is used as using particle stream.
Spallation target 3 is located at the reactor core center of reactor 4, it is preferred to use intensive ceramic particle stream target scheme, the selection of its particle
For the material that neutron yield is high, fusing point is high, thermal capacitance is big, such as radiation hardness, resistant to elevated temperatures carbide, nitride or oxide ceramics
Material is (for example：Zirconium oxide, aluminum oxide, zirconium nitride, carborundum etc., and be made up of these material blends radiation hardness, resistance to height
Adiabator), diameter is in millimeter magnitude.Its basic functional principle is, the particle of flowing is both spallation target material and cooling medium,
Particle produces wide power spectrum neutron by the bombardment of high energy proton line, and the line deposition torrid zone is gone out into target area by flowing, carry out from
Line radiates.Fluidization solid particle target has the ability for bearing 10MW~30MW beam powers.Particle stream target has liquid target simultaneously
With the feature of solid target, the inherent defect that can not only overcome the liquid spallation targets such as mercury, LBE (liquid lead bismuth alloy) to exist, and
And can effectively solve the problem that the hot removal problem of high power of solid target.In reactor 4 thermal power of reactor core be about 600MW~
2000MW, in low helium pressure environment, cooling agent particle is flowed through in reactor fuel component by fuel member under gravity
What part was constituted is vertically arranged cooling duct, the heat derives that will be produced in reactor fuel element.Coolant outlet temperature may be configured as
650~900 DEG C or so, the outlet temperature of high cooling agent ensure that the electrical efficiency of heap, and these optimizations substantially increase the warp of system
Ji property.The operation of reactor takes 20-30 long periods to reload strategy, and nuclear fuel can choose presurized water reactor spentnuclear fuel and depleted uranium
Carbide ceramics fuel.
The effect of target material after-treatment device 5 and reactor coolant after-treatment device 7 is by reacted target respectively
Particle flowing coolant after material and cooling reactor core carries out dedusting, sorting, removes a small amount of disintegrating slag wherein produced by long-play
And dust etc..
The effect of target heat-exchange system 6 and reactor heat-exchange system 8 is by the target particle after being reacted in spallation target 3 and anti-
The heat for answering the Core cooling agent particle of heap 4 to be taken out of carries out heat exchange, waste heat is exported, it is ensured that fluidization solid particle in system
Within rational temperature range, the heat after export can carry out production capacity generating.The particle heat-exchanger rig of the embodiment of the present invention can
Using several form structures such as roller cooler, fluid-bed heat exchanger, plate type heat exchanger, wherein it is preferred that plate type heat exchanger structure.
Target particle and cooling agent after post processing and heat exchange can be again injected into spallation target 3 and reactor 4 by lifting device
Carry out subsequent cycle.
Fig. 3 be the Accelerator driven of the embodiment of the present invention nuclear power system in fuel reproduction post processing subsystem schematic diagram,
The nuclear fuel processing procedure of the present invention is that the process for the spentnuclear fuel through separating at high temperature being processed into transmuting fuel, i.e. exclusive segment split
Become product, mainly neutron toxicity nucleic, this process is not present the enrichment of fissioner, its radioactivity can be greatly reduced, this
The increase of nuclear proliferation difficulty and action of terror risk is set to decline to a great extent.Embodiments of the invention mainly use simple dry method to post-process
Technology makes full use of the uranium resource in nuclear fuel, and basic ideas are to divide from LWR (light-water reactor) spentnuclear fuel involucrum layer
Separating out spentnuclear fuel pellet, --- oxidation --- reduction --- powdered spentnuclear fuel sinters new nuclear fuel into through compressing, so that again
Secondary to utilize, all processes are carried out in the hot cell of shielding, and the product extracted is efficient by physical method and ionic liquid method
Lanthanide series is separated, the main nucleic based on neutron toxicity is obtained, surplus material can reuse to improve making for fuel
With rate.
Detailed process is as shown in figure 3, nuclear fuel in burner 2 after burned for long time is from burner subsystem 101
Drawn off in the reactor core of nuclear reactor 4, be transported to fuel reproduction post processing subsystem 102, need to be handled by following steps：
(1) spentnuclear fuel pellet is isolated from spentnuclear fuel involucrum layer, the method centrifuged using pyro-oxidation-reduction and physics is segmented
Change spentnuclear fuel, remove volatile fission product and gas, it is weary that this step can add the core discarded in other reactors after burning
Expect that A1 (core weary material of such as light water reactor) together handles (H1)；(2) fission such as rare earth element is further excluded using high-temperature dry
Product, the elimination factor of fission product is more than 50% (H2)；(3) it is the fission product after exclusion is further by Rare Earth Separation method again
The rich rare earth of separation and transuranic element, are the transuranium member in final disposal thing (A2), final disposal thing (A2) by rich rare-earth transition
Cellulose content is less than 0.1% (H3)；(4) the final disposal thing (A2) of premenstrual 3 step processing can store up progress simply by dry type
Disposal, and remaining transuranic element, particularly time actinium series nucleic are reclaimed again after H3 step separation, with high-temperature oxydation before also
The weary material of major part after original is regenerated as carbide particle fuel (H4) by carbonization together；(5) granular fuel (diameter range
0.01mm~0.1mm) it is fitted into the involucrum of composite material of silicon carbide, generative fuel (H5) is made by sintering again；(6) regeneration combustion
Material is reentered to be burnt (H6) in the burner 2 of combustion subsystem 101.So carry out core weary material and nuke rubbish processing and
The regeneration cycle of nuclear fuel.
It is as follows that the nuclear power system of example of the present invention implements process：
The operation of this nuclear power system is initially that one or more superconduction straight line high current proton precessional magnetometer 1 drives a burner 2,
Now the burner 2 of the system is operated in subcritical state.Superconduction straight line high current proton precessional magnetometer 1 produces high current, high-power matter
Beamlet, proton beam continuously bombards Spallation target 3 and produces high flux neutron, and these high-throughout neutrons act on reactor
On fuel assembly in 4 reactor cores, make to continue chain reaction in reactor 4, so as to reach the purpose of production capacity and transmuting nuke rubbish.
Reacted target particle and reactor coolant can pass through target material after-treatment device 5 and reactor coolant respectively
After-treatment device 7 carries out the processing such as dedusting, sorting, removes wherein because of a small amount of disintegrating slag and dust of long-play generation etc..
Next target particle and reactor coolant by post processing respectively enter target heat-exchange system 6 and reactor heat exchange
Heat exchange is carried out in system 8, by heat derives, fluidization solid particle is reduced within certain temperature range after heat exchange, it
Satisfactory target particle and reactor coolant are refilled in spallation target 3 and reactor 4 respectively by lifting device afterwards
Next circulation is carried out, derived heat generates electricity for production capacity.
Nuclear fuel in burner 2 after burned for long time is removed from the reactor core of nuclear reactor 4 of burner subsystem 101
Go out, be transported to fuel reproduction post processing subsystem 102, after step as shown in Figure 3 is handled, reenter burning
Burnt in the burner 2 of subsystem 101, to realize the transmuting of core weary material and the regeneration cycle of nuclear fuel.
Burner passes through the subcritical operation of 3~5 years, and nuclear fuel switchs to critical conduction mode operation after certain propagation.It is super
Lead straight line high current proton precessional magnetometer 1 and cut off its external neutrons source driving to burner 2, burner 2 is completely transformed into self-holding combustion
Burning state, the now burner 2 i.e. operation is under critical conditions.At the same time, the superconduction straight line high current proton precessional magnetometer 1 again with
Another burner 2 is coupled, and it is driven, and reconstitutes a subcritical reactor, is thusly-formed an accelerator 1 and is driven
Move the pattern of several burners 2.More than one accelerator of the economy of the pattern only accelerates to drive the economy of a sub-critical reactor
Property it is high.Distinguish the pattern that driving number platform burner 2 is run parallel, more economy according to many accelerators 1.Moreover, each
Core weary material for remainder can be used as the fresh fuel of enlarging heap.
The nuclear power system of Accelerator driven includes：Burner subsystem and nuclear fuel regeneration post processing subsystem.Wherein, fire
Burner subsystem is main by device groups such as high current superconducting proton linac, high power Spallation target and modular high temperature fast reactors
Into；Nuclear fuel regeneration post processing subsystem is mainly produced by economy nuke rubbish high-temperature post-treatment flow, new nuclear fuel
Flow (production of such as fuel element and its involucrum) process is realized.The burner subsystem of the embodiment of the present invention can be by many
Platform superconduction straight line high current proton precessional magnetometer drives the accelerator redundant mode of many burners.The accelerator of the embodiment of the present invention drives
Dynamic nuclear power system may operate at subcritical, also may operate under critical condition.Just during dress heap, superconduction straight line high current Proton emission is needed
Device driving burner is burnt, and the system is run under subcritical state, after running 3~5 years, superconduction straight line high current proton
Accelerator cuts off its external neutrons source driving to burner, and burner is completely transformed into self-sustaining burning state, now the system
As run under critical conditions.
The transmuting of Accelerator driven nuclear power system collection nuke rubbish, Nuclear fuel breeding and the nuclear energy safety in production of the present invention is one
Body, is a kind of strategic energy for providing more than one thousand years safety, low emission, high performance-price ratio.For waste material transmuting：In different abundance MA
Under (secondary actinium series nucleic) fuel, its MA transmuting supports ratio between 1~12, and the waste material that system is produced is neutron toxicity nucleic.It is right
In Nuclear fuel breeding：System fuel breeding ratio ＞=1.2, the ability with propagation Pu；There is large development in Isotope production
Space, when the accelerator redundant mode of many sub-critical reactor operations of many Accelerator drivens is extended to this system, system possesses
The ability of volume production isotope.For nuclear energy production：When the operation of accelerator redundant mode is extended to this system, including outer neutron
Under the energy use in source, its capacity efficiency will maintain an equal level with current presurized water reactor；Involved content, can on the basis of uranium element in text
More than one thousand years safety, low emission, the strategic energy of high performance-price ratio are provided, if using thorium fuel, energy total amount can be increased considerably.
The beneficial effect of embodiments of the invention：
1) collect multi-functional operation, effectively the various possible fertile materials including simply dealt spentnuclear fuel are changed
For nuclear fuel, the nuclear fission energy of more than one thousand years is supported；Transmuting, deep burnup also make core while burning up most long-life nuke rubbish
Amount of waste seldom, is easy to dispose and managed.
2) security of system：The sub-critical reactor inherent safety of system ensures can shutdown automatically, high temperature nuclear reactor under accident conditions
Design using passive residual heat discharge system run than existing reactor safety and reliability, reactor simultaneously transmuting, breed
Make "hot" material inside and outside heap limited with production capacity, the accident treatment of extremely low probability can be limited in control area.
3) economy：New system reduces the expense to fuel and post processing, and hot operation improves sub-critical reactor production capacity
Efficiency is additionally consumed energy with offset accelerator, and factory's manufacture of modularization heap, the refulling cycle of extension heap, which are reduced, to be made, run and provide
Originally the cost raised, these optimizations greatly improve the cost performance of system.
4) nuclear fuel security：It is to exclude most of fission that spentnuclear fuel through separating at high temperature, which is processed into fresh fuel process,
Product, enrichment in the absence of fissioner and is greatly reduced its radioactivity, and this makes the increase of nuclear proliferation difficulty and action of terror risk
Decline to a great extent.
Claims (13)
1. a kind of nuclear power system, including：
First reactor and neutron-producing target, it is anti-that the neutron produced by neutron-producing target makes the first reactor carry out core under subcritical state
Should, and after the expiration of the predetermined period of time, the first reactor carries out nuclear reaction under critical conditions.
2. nuclear power system according to claim 1, in addition to：
Second reactor, the neutron produced by neutron-producing target makes the second reactor carry out nuclear reaction under subcritical state, and
After the expiration of the predetermined period of time, the second reactor carries out nuclear reaction under critical conditions.
3. nuclear power system according to claim 1 or 2, in addition to：
Proton precessional magnetometer, the proton precessional magnetometer produces proton beam, and the proton beam incident neutron produced by proton precessional magnetometer
Target, produces neutron,
It is preferred that the strength range for the proton beam that proton precessional magnetometer is produced is 800MeV~1500MeV.
4. nuclear power system according to claim 1, wherein：
The flux for the neutron that neutron-producing target is produced is 1E+18n/s~3E+18n/s；
Neutron-producing target includes ceramic particle, and the ceramic particle can bear 10MW~30MW beam powers；
The particle diameter of ceramic particle is in millimeter magnitude；And/or
Under at least one in subcritical state and critical condition, the thermal power of the reactor core of the first reactor for 600MW~
2000MW。
5. nuclear power system according to claim 1, in addition to：
Solid particle, is cooled down using the solid particle as cooling media to the first reactor, subcritical state and is being faced
Under at least one in boundary's state, temperature of the cooling media in the outlet of the first reactor is 650~900 DEG C.
6. nuclear power system according to claim 1, in addition to：
Fuel reproduction for core weary material processing post-processes subsystem；And/or
The nuclear power system is nuclear reactor system.
7. a kind of method for controlling nuclear power system, including：
The neutron produced by neutron-producing target makes the first reactor carry out nuclear reaction under subcritical state；And
After the expiration of the predetermined period of time, the first reactor carries out nuclear reaction under critical conditions.
8. the method for control nuclear power system according to claim 7, in addition to：
The neutron produced by neutron-producing target makes the second reactor carry out nuclear reaction under subcritical state.
9. the method for control nuclear power system according to claim 8, in addition to：
After the expiration of the predetermined period of time, the second reactor carries out nuclear reaction under critical conditions.
10. the method for the control nuclear power system according to claim 7 or 8, in addition to：
Proton beam is produced using proton precessional magnetometer；And
The proton beam incident neutron target produced by proton precessional magnetometer, produces neutron,
It is preferred that the strength range for the proton beam that proton precessional magnetometer is produced is 800MeV~1500MeV.
11. the method for control nuclear power system according to claim 7, wherein：
The flux for the neutron that neutron-producing target is produced is 1E+18n/s~3E+18n/s；
Neutron-producing target includes ceramic particle, and the ceramic particle can bear 10MW~30MW beam powers；
The particle diameter of ceramic particle is in millimeter magnitude；And/or
Under at least one in subcritical state and critical condition, the thermal power of the reactor core of the first reactor for 600MW~
2000MW。
12. the method for control nuclear power system according to claim 7, in addition to：
The first reactor is cooled down as cooling media using solid particle, in subcritical state and critical condition extremely
Under few one, temperature of the cooling media in the outlet of the first reactor is 650~900 DEG C.
13. the method for control nuclear power system according to claim 7, wherein：
The nuclear power system is nuclear reactor system.
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Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101061552A (en) * | 2002-10-25 | 2007-10-24 | 通用原子公司 | System and method for radioactive waste destruction |
| CN103096610A (en) * | 2012-12-11 | 2013-05-08 | 中国科学院近代物理研究所 | Coupling system of accelerator and windowless spallation target interface and liquid level stabilizing method |
| CN103533740A (en) * | 2013-03-04 | 2014-01-22 | 中国科学院近代物理研究所 | Target device for neutron generating device, accelerator-driven neutron generating device and beam coupling method of accelerator-driven neutron generating device |
| CN104167226A (en) * | 2014-09-05 | 2014-11-26 | 中国科学院合肥物质科学研究院 | Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test |
| CN104464842A (en) * | 2014-12-22 | 2015-03-25 | 中国科学院合肥物质科学研究院 | Accelerator driven lead bismuth cooling subcritical traveling wave reactor |
| CN104751906A (en) * | 2015-02-13 | 2015-07-01 | 中国科学院近代物理研究所 | Heat exchange system and nuclear reactor system |
| CN205004048U (en) * | 2015-09-09 | 2016-01-27 | 中国科学院近代物理研究所 | Reactive control system and nuclear reactor |
| US20160027534A1 (en) * | 2013-03-15 | 2016-01-28 | Sutherland Cook ELLWOOD | Accelerator-driven subcritical reactor system |
| CN105788666A (en) * | 2014-12-23 | 2016-07-20 | 福建福清核电有限公司 | Nuclear reactor critical process control method |
-
2017
- 2017-05-11 CN CN201710329665.0A patent/CN107146641A/en active Pending
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101061552A (en) * | 2002-10-25 | 2007-10-24 | 通用原子公司 | System and method for radioactive waste destruction |
| CN103096610A (en) * | 2012-12-11 | 2013-05-08 | 中国科学院近代物理研究所 | Coupling system of accelerator and windowless spallation target interface and liquid level stabilizing method |
| CN103533740A (en) * | 2013-03-04 | 2014-01-22 | 中国科学院近代物理研究所 | Target device for neutron generating device, accelerator-driven neutron generating device and beam coupling method of accelerator-driven neutron generating device |
| US20160027534A1 (en) * | 2013-03-15 | 2016-01-28 | Sutherland Cook ELLWOOD | Accelerator-driven subcritical reactor system |
| CN104167226A (en) * | 2014-09-05 | 2014-11-26 | 中国科学院合肥物质科学研究院 | Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test |
| CN104464842A (en) * | 2014-12-22 | 2015-03-25 | 中国科学院合肥物质科学研究院 | Accelerator driven lead bismuth cooling subcritical traveling wave reactor |
| CN105788666A (en) * | 2014-12-23 | 2016-07-20 | 福建福清核电有限公司 | Nuclear reactor critical process control method |
| CN104751906A (en) * | 2015-02-13 | 2015-07-01 | 中国科学院近代物理研究所 | Heat exchange system and nuclear reactor system |
| CN205004048U (en) * | 2015-09-09 | 2016-01-27 | 中国科学院近代物理研究所 | Reactive control system and nuclear reactor |
Non-Patent Citations (2)
| Title |
|---|
| 徐雅晨等: "加速器驱动次临界系统(ADS)及其散裂靶的研究现状", 《核科学与技术》 * |
| 李辉波等: "高温氧化挥发法_一种先进乏燃料后处理的首端工艺技术", 《原子能科学技术》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107767966A (en) * | 2017-11-29 | 2018-03-06 | 中国科学院近代物理研究所 | Nuclear reactor system |
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