CN109830315A - A kind of expansion nuclear reactor - Google Patents
A kind of expansion nuclear reactor Download PDFInfo
- Publication number
- CN109830315A CN109830315A CN201910085838.8A CN201910085838A CN109830315A CN 109830315 A CN109830315 A CN 109830315A CN 201910085838 A CN201910085838 A CN 201910085838A CN 109830315 A CN109830315 A CN 109830315A
- Authority
- CN
- China
- Prior art keywords
- bar
- gather
- nuclear reactor
- pellet
- reactor
- 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.)
- Granted
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention proposes a kind of expansion nuclear reactors, belong to nuclear reactor technology field, more particularly to a kind of expansion nuclear reactor.When solving that the cooling material that is caused is lost under burst fortuitous event, the problem of the serious nuclear accident such as reactor core caused by reactor cannot stop working in time melts.It includes the pellet unit and expanding unit of multiple radially cuttings.It is mainly used for realizing the autonomous separation of reactor core.
Description
Technical field
The invention belongs to nuclear reactor technology fields, more particularly to a kind of expansion nuclear reactor.
Background technique
In low temperature heating reactor or the design of small modular reactor, reactor is integrally immersed in pond.In pond
Water provides the safety guarantee of reactor as ultimate heat sink.But it since there are the risks that earthquake etc. surprisingly occurs, builds on ground
The pond of table is likely to occur crack, and the water in pond is caused to flow out, can not shutdown so that reactor system is possibly in accident
In the case where lose ultimate heat sink, enough coolings can not be provided, and then generate a large amount of heat not being discharged, reactor core occurs and melts
Solution, leads to serious nuclear accident.
Summary of the invention
The present invention in order to solve the problems in the prior art, proposes a kind of expansion nuclear reactor.
To achieve the above object, the invention adopts the following technical scheme: a kind of expansion nuclear reactor, it includes more
The pellet unit and expanding unit of a radially cutting, pellet unit bottom surface and reactor bottom are hinged, the multiple core
Module unit, which radially polymerize, forms reactor core, the expanding unit include it is multiple gather bar and restraint assembly, it is described to gather bar quantity
Identical as pellet element number and pellet unit with corresponding position is fixedly linked, and the multiple bar of gathering is along reactor central axes
Gather the complete cylindrical body of composition to top, described to gather for fastening section at the top of bar, the fastening section lower section is the heat dissipation for gathering bar
Section, the restraint assembly are located at and gather at bar fastening section, and the restraint assembly gathers bar and be connected under buoyancy with each,
Make it is each gather closely connected between bar, realize the polymerization of pellet unit, the restraint assembly realizes pellet under the effect of gravity
The separation of unit.
Further, the bar fastening section diameter of gathering is greater than radiating segment diameter.
Further, the restraint assembly is with garter spring jaggy, and the garter spring is buoyancy garter spring.
Further, the bar fastening section of gathering is floating box structure, provides upward buoyancy to gather bar.
Further, the restraint assembly is separation supporting mechanism, the separation supporting mechanism include weight with
Support rod, the weight are located inside floating box structure, and the support rod quantity is identical as pellet element number, the bearing
Bar one end and weight bottom surface are hinged, the other end and corresponding position to gather bar middle section hinged.
Further, the pellet unit for the whole involucrum pellet with common envelope or is respectively provided with independent involucrum
Independent involucrum pellet.
Further, the bar fastening section top of gathering is provided with stop tab.
Further, the cooling fin gathered bar heat dissipation section surface and be provided with venetian blind type protrusion.
Further, described to gather bar radiating segment using heat-conducting type metal material or use heat-conducting type metal coating.
Further, the pellet unit fuel uses the direct arrangement architecture of fuel element or fuel assembly structure.
Compared with prior art, the beneficial effects of the present invention are: the present invention using expansion nuclear reactor structure come
When the cooling material for solving to be caused under burst fortuitous event is lost, reactor core caused by reactor cannot stop working in time melts
The problem of etc. serious nuclear accident.It introduces and passively replaces people by means of natural laws such as gravity, buoyancy with passive shutdown mechanism
Industry control system and redundance unit so that reactor occur cooling material lose situation in can autonomous action, be unfolded reactor core, realize
Automatic shutdown, enhancing heat dissipation avoid reactor core from melting the generation for waiting major accidents.The present invention is not necessarily to when the fortuitous event that happens suddenly occurs
Human response is not necessarily to control system, realizes complete passive and passive behavior, simplifies system, improve immersion core
The inherent safety of reactor.
Detailed description of the invention
Fig. 1 is a kind of expansion nuclear reactor restraint assembly of the present invention when being garter spring, and rounding state structure is shown
It is intended to
Fig. 2 is a kind of expansion nuclear reactor restraint assembly of the present invention when being garter spring, and unfolded state structure is shown
It is intended to
Fig. 3 is that a kind of expansion nuclear reactor restraint assembly of the present invention is to collapse shape when separating supporting mechanism
State structural schematic diagram
Fig. 4 is that a kind of expansion nuclear reactor restraint assembly of the present invention is that shape is unfolded when separating supporting mechanism
State structural schematic diagram
Fig. 5 is a kind of expansion nuclear reactor unfolded state schematic diagram of the present invention
Fig. 6 is a kind of expansion nuclear reactor entirety involucrum pellet structural schematic diagram of the present invention
Fig. 7 is a kind of expansion nuclear reactor independence involucrum pellet structural schematic diagram of the present invention
1- horizontal plane, 2- stop tab, 3- garter spring, 4- gather bar, 5- cooling fin, 6- pellet unit, 7- reactor bottom, 8-
Buoyancy tank, 9- weight, 10- support rod, 11- entirety involucrum pellet, 12- independence involucrum pellet, 13- fuel element directly arrange
Structure, 14- fuel assembly structure
Specific embodiment
Following will be combined with the drawings in the embodiments of the present invention, and technical solution in the embodiment of the present invention carries out clear, complete
Site preparation illustrates.
Illustrate present embodiment referring to Fig. 1-7, a kind of expansion nuclear reactor, it includes multiple radially cuttings
Pellet unit 6 and expanding unit, 6 bottom surface of pellet unit and reactor bottom 7 are hinged, and the multiple pellet unit 6 is along diameter
Form reactor core to polymerization, the expanding unit include it is multiple gather bar 4 and restraint assembly, it is described to gather 4 quantity of bar and pellet list
The identical and pellet unit 6 with corresponding position of first 6 quantity is fixedly linked, the multiple to gather bar 4 along reactor central axes to top
Portion gathers the complete cylindrical body of composition, and described to gather for fastening section at the top of bar 4, the fastening section lower section is the radiating segment for gathering bar 4,
The restraint assembly is located at and gathers at 4 fastening section of bar, and the restraint assembly is connected under buoyancy with each bar 4 of gathering,
Make it is each gather closely connected between bar 4, realize the polymerization of pellet unit 6, the restraint assembly realizes core under the effect of gravity
The separation of module unit 6.
In the present embodiment under normal operating conditions, reactor is integrally immersed in cooling medium, the multiple to gather bar 4
Gather the complete cylindrical body of composition to top along reactor central axes, each pellet unit 6 is gathered around central axes, and reactor is referring to
There are enough fissile material in fixed space, enough netron-flux densities may be implemented, realizes fission, the normal work of reactor
Make；When under emergency conditions, cooling medium is lost, and the multiple 4 upper end constraint relief of bar of gathering divides under the effect of gravity
From each pellet unit 6 being unfolded outward around 7 hinged place of reactor bottom, due to neutron leakage or specified in reactor
Space in fission material mass it is insufficient and stop fission, reactor stops working, and realizes the automatic shutdown of reactor.
Gather 4 fastening section diameter of bar described in the present embodiment and is greater than radiating segment diameter, for reinforcing the heat dissipation of heap core segment,
It is conducive to constraint of the restraint assembly releasing to bar 4 is gathered simultaneously, the restraint assembly is with garter spring 3 jaggy, and the garter spring 3 is
Buoyancy garter spring, the buoyancy garter spring can be such that multiple 4 phases of bar of gathering gather in buoyancy float downward to fastening section, be situated between when cooling
Matter lose when, liquid level decline, buoyancy garter spring can under floating to be detached from fastening section, and from 3 indentation, there of garter spring disengaging gather bar 4, release
The constraint for gathering bar 4 is made to gather the separation of bar 4, reactor stops working.
Gathering 4 fastening section of bar described in the present embodiment is 8 structure of buoyancy tank, provides upward buoyancy to gather bar 4, it is described about
Tread assembly is separation supporting mechanism, and the separation supporting mechanism includes weight 9 and support rod 10, the weight 9
In 8 inside configuration of buoyancy tank, 10 quantity of support rod is identical as 6 quantity of pellet unit, described 10 one end of support rod and gravity part
9 bottom surface of part is hinged, and the other end and corresponding position gather that 4 middle section of bar is hinged, and the weight 9 can be by under self gravity
Drop pushes support rod 10 to strut the bar 4 of gathering to gather together, and bar 4 is respectively gathered in release makes its separation.When reactor integrally soaks
When not in cooling medium, 8 structure of buoyancy tank provides upward buoyancy, with the downward gravity of weight 9 be in equilibrium state or
Slightly larger than gravity, gather state so that gathering bar 4 and being in；When cooling medium is lost, liquid level decline causes part buoyancy tank 8 to occur
On liquid level, the provided loss of buoyancy of buoyancy tank 8 or reduction, the gravity that weight 9 provides are floated greater than what buoyancy tank 8 can be generated
Power, top weight 9 decline by self gravity, and support rod 10 is pushed to strut the bar 4 of gathering to gather together, and then will
Each pellet unit 6 separates, and realizes the automatic shutdown of reactor.Or under emergency conditions, reactor cooling condition is disliked
Change, coolant temperature increases, and density decline, the buoyancy that buoyancy tank 8 can be generated reduces, and also results in the offer of weight 9
Gravity be greater than the buoyancy that can be generated of buoyancy tank 8, weight 9 declines, will gather bar 4 by support rod 10 and strut, and make each
Pellet unit 6 separates, and realizes the automatic shutdown of reactor.Gathering bar 4 can also be used auxiliary fastening means, in normal running (operation) conditions
Under, bar gathering will be gathered when reactor is integrally immersed in cooling medium, reduces system mode disturbance；Under emergency conditions, liquid
Face decline or fluid density reduce, and the gravity that weight 9 provides is enough to strut auxiliary secure component, realize above-mentioned function.
Based on the above embodiment, pellet unit described in the present embodiment 6 is the whole involucrum pellet 11 with common envelope
Or it is respectively provided with independent involucrum, the independent involucrum pellet 12 formed by the individual that involucrum separates, 6 fuel of pellet unit uses
The direct arrangement architecture 13 of fuel element or fuel assembly structure 14, when using fuel element direct arrangement architecture 13, preferred core
Reactor core is along the circumferential direction divided into six by module unit 6；When using fuel assembly structure 14, preferred pellet unit 6
Reactor core is along the circumferential direction divided into four.The 4 fastening section top of bar of gathering is provided with stop tab 2, for preventing
Restraint assembly slips, the cooling fin 5 gathered the heat dissipation section surface of bar 4 and be provided with venetian blind type protrusion, for increasing radiating surface
Product, it is described to gather 4 radiating segment of bar using heat-conducting type metal material or use heat-conducting type metal coating, for improving heat dissipation effect,
The restraint assembly selects light-weight high-strength material processing preparation.
Above to a kind of expansion nuclear reactor provided by the present invention, it is described in detail, it is used herein
A specific example illustrates the principle and implementation of the invention, and the above embodiments are only used to help understand
Method and its core concept of the invention；At the same time, for those skilled in the art is having according to the thought of the present invention
There will be changes in body embodiment and application range, in conclusion the content of the present specification should not be construed as to the present invention
Limitation.
Claims (10)
1. a kind of expansion nuclear reactor, it is characterised in that: it includes pellet unit (6) and the exhibition of multiple radially cuttings
Opening apparatus, hingedly, the multiple pellet unit (6) radially polymerize shape for pellet unit (6) bottom surface and reactor bottom (7)
At reactor core, the expanding unit include it is multiple gather bar (4) and restraint assembly, it is described to gather bar (4) quantity and pellet unit (6)
The identical and pellet unit (6) with corresponding position of quantity is fixedly linked, the multiple to gather bar (4) along reactor central axes to top
Portion gathers the complete cylindrical body of composition, and described to gather for fastening section at the top of bar (4), the fastening section lower section is to gather dissipating for bar (4)
Hot arc, the restraint assembly are located at and gather at bar (4) fastening section, and the restraint assembly gathers bar with each under buoyancy
(4) be connected, make it is each gather closely connected between bar (4), realize pellet unit (6) polymerization, the restraint assembly weight
The lower separation for realizing pellet unit (6) of power effect.
2. a kind of expansion nuclear reactor according to claim 1, it is characterised in that: described to gather bar (4) fastening
Section diameter is greater than radiating segment diameter.
3. a kind of expansion nuclear reactor according to claim 2, it is characterised in that: the restraint assembly be with
The garter spring (3) of notch, the garter spring (3) are buoyancy garter spring.
4. a kind of expansion nuclear reactor according to claim 1, it is characterised in that: described to gather bar (4) fastening
Section is buoyancy tank (8) structure, provides upward buoyancy to gather bar (4).
5. a kind of expansion nuclear reactor according to claim 4, it is characterised in that: the restraint assembly is separation
Supporting mechanism, the separation supporting mechanism include weight (9) and support rod (10), and the weight (9) is located at buoyancy tank
(8) inside configuration, support rod (10) quantity is identical as pellet unit (6) quantity, described support rod (10) one end and gravity
Component (9) bottom surface is hinged, the other end and corresponding position to gather bar (4) middle section hinged.
6. a kind of expansion nuclear reactor according to claim 1, it is characterised in that: the pellet unit (6) is
Whole involucrum pellet (11) with common envelope or the independent involucrum pellet (12) for being respectively provided with independent involucrum.
7. a kind of expansion nuclear reactor described in -6 according to claim 1, it is characterised in that: described to gather bar (4) tightly
Gu section top is provided with stop tab (2).
8. a kind of expansion nuclear reactor described in -6 according to claim 1, it is characterised in that: described gather bar (4) dissipate
Hot arc surface is provided with the cooling fin (5) of venetian blind type protrusion.
9. a kind of expansion nuclear reactor described in -6 according to claim 1, it is characterised in that: described gather bar (4) dissipate
Hot arc is using heat-conducting type metal material or uses heat-conducting type metal coating.
10. a kind of expansion nuclear reactor described in -6 according to claim 1, it is characterised in that: the pellet unit (6)
Fuel uses the direct arrangement architecture of fuel element (13) or fuel assembly structure (14).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910085838.8A CN109830315B (en) | 2019-01-29 | 2019-01-29 | Expanded nuclear reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910085838.8A CN109830315B (en) | 2019-01-29 | 2019-01-29 | Expanded nuclear reactor core |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109830315A true CN109830315A (en) | 2019-05-31 |
| CN109830315B CN109830315B (en) | 2022-08-02 |
Family
ID=66862787
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910085838.8A Active CN109830315B (en) | 2019-01-29 | 2019-01-29 | Expanded nuclear reactor core |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109830315B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112216409A (en) * | 2020-09-07 | 2021-01-12 | 国家电投集团科学技术研究院有限公司 | Reactor core, nuclear reactor and passive shutdown method of nuclear reactor |
Citations (20)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1042619A (en) * | 1988-09-19 | 1990-05-30 | 法玛通公司 | From the detachable conduit of fuel assembly for nuclear reactor, take out the method and apparatus of lock collar |
| JPH04212094A (en) * | 1990-04-20 | 1992-08-03 | Hitachi Ltd | Fuel assembly |
| CN101299351A (en) * | 2008-06-27 | 2008-11-05 | 张育曼 | Stack core of water-cooling double-section breeding nuclear reactor as well as nuclear reactor using the same |
| DE102011004821B3 (en) * | 2011-02-28 | 2012-04-19 | Areva Np Gmbh | Method for stabilizing blocked fuel assembly when loading/unloading core of nuclear reactor, involves compensating difference between buoyancy and gravitational forces acting on fuel assembly and moving object by buoyancy element |
| CN102667951A (en) * | 2010-08-24 | 2012-09-12 | 巴布科克和威尔科克斯核能股份有限公司 | Terminal elements for coupling connecting rods and control rods in control rod assemblies for a nuclear reactor |
| JP2012207964A (en) * | 2011-03-29 | 2012-10-25 | Japan Atomic Energy Agency | Fastening device for extracting reactor core upper part mechanism |
| CN202584749U (en) * | 2012-05-29 | 2012-12-05 | 中广核工程有限公司 | Release examining tool for driving rod of control bar for nuclear power station |
| CN103077756A (en) * | 2013-01-13 | 2013-05-01 | 中国科学院合肥物质科学研究院 | Clamp device of refueling machine for liquid heavy metal cooling pile |
| CN103165205A (en) * | 2011-12-13 | 2013-06-19 | 核动力运行研究所 | Hydraulic separating tool for jam of fuel assembly |
| CN103366836A (en) * | 2013-04-01 | 2013-10-23 | 中科华核电技术研究院有限公司 | Nuclear fuel pellet and manufacturing method thereof, and nuclear reactor |
| CN205751537U (en) * | 2016-05-06 | 2016-11-30 | 上海核工程研究设计院 | A kind of have the CRDM that can separate nut driving |
| CN106409366A (en) * | 2016-11-14 | 2017-02-15 | 清华大学天津高端装备研究院 | Grabbing device for fuel assembly |
| CN106409350A (en) * | 2016-11-02 | 2017-02-15 | 中广核研究院有限公司 | Emergency shutdown protecting system for heavy metal cooling reactor |
| CN106531233A (en) * | 2016-12-29 | 2017-03-22 | 中国科学院合肥物质科学研究院 | Reactor fuel assembly |
| KR20170032103A (en) * | 2015-09-14 | 2017-03-22 | 한국원자력연구원 | Hybrid nuclear reactor with separable core |
| CN107000039A (en) * | 2014-12-03 | 2017-08-01 | 株式会社神户制钢所 | Buoyancy transferring clamp |
| CN107112057A (en) * | 2014-12-19 | 2017-08-29 | 原子能与替代能源委员会 | Include the fuel assembly for SFR nuclear reactors of the shell containing the upper neutron shield device detachably fastened |
| CN107507653A (en) * | 2017-08-29 | 2017-12-22 | 华北电力大学 | A kind of Lead cooled fast breeder reactor separates reactor core embodiment |
| CN108231218A (en) * | 2017-12-29 | 2018-06-29 | 安徽中科超安科技有限公司 | Passive shutdown protection system for nuclear power station and other reactors |
| CN109074874A (en) * | 2016-05-02 | 2018-12-21 | 泰拉能源公司 | molten fuel nuclear reactor with neutron reflection coolant |
-
2019
- 2019-01-29 CN CN201910085838.8A patent/CN109830315B/en active Active
Patent Citations (21)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1042619A (en) * | 1988-09-19 | 1990-05-30 | 法玛通公司 | From the detachable conduit of fuel assembly for nuclear reactor, take out the method and apparatus of lock collar |
| JPH04212094A (en) * | 1990-04-20 | 1992-08-03 | Hitachi Ltd | Fuel assembly |
| CN101299351A (en) * | 2008-06-27 | 2008-11-05 | 张育曼 | Stack core of water-cooling double-section breeding nuclear reactor as well as nuclear reactor using the same |
| CN102667951A (en) * | 2010-08-24 | 2012-09-12 | 巴布科克和威尔科克斯核能股份有限公司 | Terminal elements for coupling connecting rods and control rods in control rod assemblies for a nuclear reactor |
| DE102011004821B3 (en) * | 2011-02-28 | 2012-04-19 | Areva Np Gmbh | Method for stabilizing blocked fuel assembly when loading/unloading core of nuclear reactor, involves compensating difference between buoyancy and gravitational forces acting on fuel assembly and moving object by buoyancy element |
| JP2012207964A (en) * | 2011-03-29 | 2012-10-25 | Japan Atomic Energy Agency | Fastening device for extracting reactor core upper part mechanism |
| CN103165205A (en) * | 2011-12-13 | 2013-06-19 | 核动力运行研究所 | Hydraulic separating tool for jam of fuel assembly |
| CN202584749U (en) * | 2012-05-29 | 2012-12-05 | 中广核工程有限公司 | Release examining tool for driving rod of control bar for nuclear power station |
| CN103077756A (en) * | 2013-01-13 | 2013-05-01 | 中国科学院合肥物质科学研究院 | Clamp device of refueling machine for liquid heavy metal cooling pile |
| CN103366836A (en) * | 2013-04-01 | 2013-10-23 | 中科华核电技术研究院有限公司 | Nuclear fuel pellet and manufacturing method thereof, and nuclear reactor |
| CN107000039A (en) * | 2014-12-03 | 2017-08-01 | 株式会社神户制钢所 | Buoyancy transferring clamp |
| CN107112057A (en) * | 2014-12-19 | 2017-08-29 | 原子能与替代能源委员会 | Include the fuel assembly for SFR nuclear reactors of the shell containing the upper neutron shield device detachably fastened |
| CN106531228A (en) * | 2015-09-14 | 2017-03-22 | 韩国原子力研究院 | Hybrid nuclear reactor with separable core |
| KR20170032103A (en) * | 2015-09-14 | 2017-03-22 | 한국원자력연구원 | Hybrid nuclear reactor with separable core |
| CN109074874A (en) * | 2016-05-02 | 2018-12-21 | 泰拉能源公司 | molten fuel nuclear reactor with neutron reflection coolant |
| CN205751537U (en) * | 2016-05-06 | 2016-11-30 | 上海核工程研究设计院 | A kind of have the CRDM that can separate nut driving |
| CN106409350A (en) * | 2016-11-02 | 2017-02-15 | 中广核研究院有限公司 | Emergency shutdown protecting system for heavy metal cooling reactor |
| CN106409366A (en) * | 2016-11-14 | 2017-02-15 | 清华大学天津高端装备研究院 | Grabbing device for fuel assembly |
| CN106531233A (en) * | 2016-12-29 | 2017-03-22 | 中国科学院合肥物质科学研究院 | Reactor fuel assembly |
| CN107507653A (en) * | 2017-08-29 | 2017-12-22 | 华北电力大学 | A kind of Lead cooled fast breeder reactor separates reactor core embodiment |
| CN108231218A (en) * | 2017-12-29 | 2018-06-29 | 安徽中科超安科技有限公司 | Passive shutdown protection system for nuclear power station and other reactors |
Non-Patent Citations (1)
| Title |
|---|
| 彭冠男 等: "快堆悬浮式非能动停堆组件移动体落棒性能分", 《应用科技》 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112216409A (en) * | 2020-09-07 | 2021-01-12 | 国家电投集团科学技术研究院有限公司 | Reactor core, nuclear reactor and passive shutdown method of nuclear reactor |
| CN112216409B (en) * | 2020-09-07 | 2023-02-28 | 国家电投集团科学技术研究院有限公司 | Reactor core, nuclear reactor and passive shutdown method of nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| CN109830315B (en) | 2022-08-02 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP6319916B2 (en) | Fuel assembly | |
| CN101223607B (en) | Advanced gray rod control assembly | |
| US5064607A (en) | Hybrid nuclear reactor grey rod to obtain required reactivity worth | |
| US20100296620A1 (en) | High power density liquid-cooled pebble-channel nuclear reactor | |
| EP3559956B1 (en) | Passive reactivity control in a nuclear fission reactor | |
| JP2019012073A (en) | Nuclear reactor module | |
| US3378452A (en) | Fuel assembly for fast nuclear reactors | |
| US3244597A (en) | Fast breeder neutronic reactor | |
| CN109830315A (en) | A kind of expansion nuclear reactor | |
| Suzuki et al. | Reactivity-initiated-accident analysis without scram of a molten salt reactor | |
| US3403076A (en) | Molten salt breeder reactor and fuel cell for use therein | |
| JPH0379678B2 (en) | ||
| US3338790A (en) | Fast nuclear reactor | |
| Cahalan et al. | Accommodation of unprotected accidents by inherent safety design features in metallic and oxide-fueled LMFBRs | |
| JP2003533683A (en) | Monolithic fuel element and fast spectral boiling water reactor using said element | |
| RU2497209C1 (en) | System for emergency cooldown of nuclear reactor of pond type | |
| WO2014168520A1 (en) | Fast neutron reactor utilizing a dual-phase metal system | |
| US3290221A (en) | Boiling water nuclear reactor with buoyant fuel or reflector control assembly | |
| Sienicki et al. | Passive safety of the STAR-LM HLMC natural convection reactor | |
| US11398315B2 (en) | Fuel element, fuel assembly, and core | |
| US3235464A (en) | Liquid moderated nuclear reactor core including annular control element movable about moderator filler rod | |
| Orechwa et al. | Physics implications of oxide and metal fuel on the design of small LMFBR cores | |
| EP2924689A1 (en) | Nuclear reactor | |
| Sefidvash | Fluidized bed nuclear reactor as a IV generation reactor | |
| Elgert et al. | Preliminary Investigations for an Advanced Engineering Test Reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |