CN106531232A - Fuel assembly available for integral replacement - Google Patents
Fuel assembly available for integral replacement Download PDFInfo
- Publication number
- CN106531232A CN106531232A CN201611244871.3A CN201611244871A CN106531232A CN 106531232 A CN106531232 A CN 106531232A CN 201611244871 A CN201611244871 A CN 201611244871A CN 106531232 A CN106531232 A CN 106531232A
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- CN
- China
- Prior art keywords
- fuel assembly
- fuel
- reactor
- integration
- hold
- 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.)
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a fuel assembly available for integral replacement. By fixation of the fuel assembly and a top cover, axial fixation of the fuel assembly is realized, a fuel assembly fixation problem caused by a high-density cooling agent of a liquid-state lead-based reactor is solved, and integral replacement of the fuel assembly is realized. Since fuel elements with fixed upper ends and free lower ends are reinforced under the action of axial flushing force and buoyancy of the cooling agent, stability of the fuel elements in operation of the reactor is improved; owing to a moderator filled in each fixed rod, fission neutron moderation can be accelerated to improve reactivity of a reactor core and reduce the size of the reactor core. The fuel assembly has advantages of high safety, simple structure, small reactor core size and the like.
Description
Technical field
The invention belongs to nuclear reactor field, more particularly to a kind of to can be used for the fuel assembly that integration is reloaded.
Background technology
Liquid lead-containing alloy cooled reactor fuel assembly under arms during, due to lead-containing alloy coolant density it is big,
Cause component that the gravity of itself cannot be relied on to install and fixed.The fixed of liquid lead-containing alloy cooled reactor is filled in the world at present
Put design distinguished larger, predominantly the mode such as counterweight, mechanical interlocking.The concrete grammar of counterweight is to add density more in component internal
Big weight material, so as to the combined density of component is improved solid by the gravity of itself to more than coolant, enabling the components to
It is fixed；The concrete grammar of mechanical interlocking be by the fuel rod in the middle of component is substituted for check lock lever, by with pin under component
Locking device is coordinated, so as to fixation kit.
Counterweight mode has problems and is, when the abnormal operation conditions such as earthquake occur, it may occur that the vibration of component
Or displacement, there is a possibility that interruption of service.The problem that mechanical interlocking mode is present is that component density is less than coolant,
Cannot complete to install, and due to bad environments of being on active service in reactor, the mode being mechanically fixed there may be unstable, rapid wear
Bad situations such as.
The content of the invention
The technology of the present invention solve problem：To overcome the deficiencies in the prior art, there is provided a kind of to can be used for the combustion that integration is reloaded
Material component.
The present invention solves technical problem and adopts the following technical scheme that：
A kind of to can be used for the fuel assembly that integration is reloaded, including fuel element, the fuel element upper end is fixed, lower end
Freely, the fuel element upper end plug is fixed on the upper base of fuel assembly, and hold-down bars, institute are distributed with the fuel assembly
State hold-down bars upper end to be fixed on reactor lid.
Also there are following characteristics in the present invention：
The lower end plug of the fuel element is stretched in the grate opening of the bottom nozzle.
The hold-down bars lower end is inserted in the core support screen.
Hold-down bars hollow structure in the reactor core active section height, internal filler metal berryllium moderator.
The metal berryllium moderator is metallic beryllium, zircoium hydride moderator, and moderator height is consistent with reactor core active region.
Compared with the prior art, beneficial effects of the present invention are embodied in：
(1) by the way of the fixation of fuel assembly top cover, the fixation problem that high density coolant brings is solved, and is realized
The integration of fuel assembly is reloaded.
(2) fuel element by the way of the fixation of upper end is effectively utilized the buoyancy and axial scouring force of coolant, is reduced
The stream of fuel element causes vibrations, improves the service safety of fuel element.
(3) moderator at hold-down bars center, effective slowing down neutron, improves the reactivity of reactor core, reduces reactor core dress
Doses and heap core volume.
Description of the drawings
The Figure of description for constituting the part of the application is used for providing a further understanding of the present invention, and the present invention's shows
Meaning property embodiment and its illustrated for explaining the present invention, does not constitute inappropriate limitation of the present invention.In the accompanying drawings：
Fig. 1 is that the fuel assembly structure of the present invention is illustrated.
Wherein, 1 is fuel element；2 is upper base 2；3 is bottom nozzle；4 is hold-down bars；5 is reactor lid；6 is reactor core
Support screen；7 is moderator.
Specific embodiment
It should be noted that in the case where not conflicting, the feature in embodiment and embodiment in the application can phase
Mutually combine.Below with reference to the accompanying drawings and in conjunction with the embodiments describing the present invention in detail.
With reference to Fig. 1, to architectural feature of the invention, details are as follows：
It is a kind of to can be used for the fuel assembly that reloads of integration, by a number of fuel element 1, upper base 2, bottom nozzle 3,
The assembling of hold-down bars 4 forms overall structure；The integration fuel assembly that reloads is fixed using top cover, and fuel element 1 is fixed using upper end,
The free fixed form in lower end；Several hold-down bars 4 are distributed with inside fuel assembly, 4 upper end of hold-down bars is directly anchored to reactor
On top cover 5,1 lower end of hold-down bars is inserted in reactor core support screen 6；4 inside filler metal beryllium of fuel assembly hold-down bars,
The moderators such as zircoium hydride 7, the height of moderator 7 are highly consistent with reactor core active region；Fuel element 1 is fixed using upper end, lower end
Free mode, 1 upper end plug of fuel element are fixed with upper pipe seat of fuel component 2, under 1 time end plug insertion fuel assembly of fuel element
In the grid hole of base 2, but do not fix, with the axial stretching during ensureing fuel rod under arms.
Fuel assembly is fixed and reactor lid 5 using hold-down bars 1, can solve the combustion caused due to high density coolant
The problem that material component cannot be fixed, it is ensured that safety of the fuel assembly in running, it is possible in cold-refueling, pass through
The mode for opening reactor lid 5 realizes that integration is reloaded.
In liquid lead base reactor operation, fuel element 1 is subject to the buoyancy of lead base coolant and axial scouring force, adopts
Being fixed on upper base 2 with fuel element 1 can utilize the buoyancy and axial scouring force of coolant to be fixed fuel element 1,
Reduce stream of the fuel element 1 in running and cause seismism, it is ensured that the military service safety of fuel element 1.
Using the moderator at 4 center of hold-down bars, can effective slowing down fission neutron, improve the quantity of thermal neutron, increase anti-
Ying Xing, so as to effectively reduce core loading amount and heap core volume.
The integration of design is reloaded fuel assembly, and fuel assembly is during the time it is carried out, can be by opening reactor lid 5 once
Component proposes by property, realizes that integration is reloaded；The mode fixed with reactor lid 5 solves fuel assembly in reactor operation
During fixation problem, improve the safety of fuel assembly；Simultaneously the metallic beryllium inside hold-down bars 4 can effectively in slowing down
Son, improves the reactivity of reactor, reduces fuel charge amount and heap core volume.
Non-elaborated part of the present invention belongs to techniques well known.
It is obvious to a person skilled in the art that the invention is not restricted to the details of above-mentioned one exemplary embodiment, Er Qie
In the case of spirit or essential attributes without departing substantially from the present invention, the present invention can be realized in other specific forms.Therefore, no matter
From the point of view of which point, embodiment all should be regarded as exemplary, and be nonrestrictive, the scope of the present invention is by appended power
Profit is required rather than described above is limited, it is intended that all in the implication and scope of the equivalency of claim by falling
Change is included in the present invention.Any reference in claim should not be considered as and limit involved claim.
Moreover, it will be appreciated that although this specification is been described by according to embodiment, not each embodiment is only wrapped
Containing an independent technical scheme, this narrating mode of description is only that those skilled in the art should for clarity
Using description as an entirety, the technical scheme in each embodiment can also Jing it is appropriately combined, form those skilled in the art
Understandable other embodiment.
Claims (5)
- It is 1. a kind of to can be used for the fuel assembly that integration is reloaded, it is characterised in that：Including fuel element (1), the fuel element (1) upper end fix, lower end freedom, fuel element (1) upper end plug is fixed on the upper base (2) of fuel assembly, the combustion Hold-down bars (4) is distributed with material component, hold-down bars (4) upper end is fixed on reactor lid (5).
- It is 2. according to claim 1 to can be used for the fuel assembly that integration is reloaded, it is characterised in that：The fuel element (1) lower end plug is stretched in the grate opening of the bottom nozzle (3).
- It is 3. according to claim 2 to can be used for the fuel assembly that integration is reloaded, it is characterised in that：The hold-down bars (4) Lower end is inserted in the core support screen (6).
- It is 4. according to claim 3 to can be used for the fuel assembly that integration is reloaded, it is characterised in that：The hold-down bars (4) The hollow structure in the reactor core active section height, internal filling moderator (7).
- It is 5. according to claim 4 to can be used for the fuel assembly that integration is reloaded, it is characterised in that：The moderator (7) For metallic beryllium or zircoium hydride, the moderator height is consistent with reactor core active region.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201611244871.3A CN106531232B (en) | 2016-12-29 | 2016-12-29 | A kind of fuel assembly that can be used for integration to reload |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201611244871.3A CN106531232B (en) | 2016-12-29 | 2016-12-29 | A kind of fuel assembly that can be used for integration to reload |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106531232A true CN106531232A (en) | 2017-03-22 |
| CN106531232B CN106531232B (en) | 2017-09-22 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201611244871.3A Active CN106531232B (en) | 2016-12-29 | 2016-12-29 | A kind of fuel assembly that can be used for integration to reload |
Country Status (1)
| Country | Link |
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| CN (1) | CN106531232B (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110853774A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor |
| CN111128411A (en) * | 2019-12-31 | 2020-05-08 | 中国科学院合肥物质科学研究院 | Small-size solid state reactor core |
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|---|---|---|---|---|
| JPH032691A (en) * | 1989-05-31 | 1991-01-09 | Nuclear Fuel Ind Ltd | Fuel assembly for boiling water reactor |
| US5349618A (en) * | 1992-09-09 | 1994-09-20 | Ehud Greenspan | BWR fuel assembly having oxide and hydride fuel |
| CN101154472A (en) * | 2006-09-29 | 2008-04-02 | 中国核动力研究设计院 | Integrated low-temperature nuclear heat supplying pile |
| CN102117668A (en) * | 2009-12-31 | 2011-07-06 | 中国核动力研究设计院 | Reactor core unloading tool |
| CN102610286A (en) * | 2012-03-30 | 2012-07-25 | 中国科学院合肥物质科学研究院 | Fuel subassembly fixing device of reloadable liquid heavy metal reactor |
| CN103117098A (en) * | 2013-02-04 | 2013-05-22 | 中国核动力研究设计院 | Square fuel assembly structure suitable for supercritical water-cooled reactor |
| CN103310855A (en) * | 2013-05-23 | 2013-09-18 | 中国科学院合肥物质科学研究院 | Liquid heavy metal cooling reactor fuel assembly |
| JP2015059791A (en) * | 2013-09-18 | 2015-03-30 | 株式会社東芝 | Fast reactor core and fast reactor comprising the core |
| KR101549603B1 (en) * | 2015-02-25 | 2015-09-02 | 한국과학기술원 | A passive safety device and a nuclear fuel assembly with the passive safety device |
| RU2014112921A (en) * | 2014-04-02 | 2015-10-10 | Открытое акционерное общество "Центральное конструкторское бюро машиностроения" | FUEL ASSEMBLY |
| CN105210151A (en) * | 2013-03-15 | 2015-12-30 | 赛瑞丹公司 | Method of cooling nuclear reactor and nuclear reactor including polyhedral boron hydride or carborane anions |
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2016
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| JPH032691A (en) * | 1989-05-31 | 1991-01-09 | Nuclear Fuel Ind Ltd | Fuel assembly for boiling water reactor |
| US5349618A (en) * | 1992-09-09 | 1994-09-20 | Ehud Greenspan | BWR fuel assembly having oxide and hydride fuel |
| CN101154472A (en) * | 2006-09-29 | 2008-04-02 | 中国核动力研究设计院 | Integrated low-temperature nuclear heat supplying pile |
| CN102117668A (en) * | 2009-12-31 | 2011-07-06 | 中国核动力研究设计院 | Reactor core unloading tool |
| CN102610286A (en) * | 2012-03-30 | 2012-07-25 | 中国科学院合肥物质科学研究院 | Fuel subassembly fixing device of reloadable liquid heavy metal reactor |
| CN103117098A (en) * | 2013-02-04 | 2013-05-22 | 中国核动力研究设计院 | Square fuel assembly structure suitable for supercritical water-cooled reactor |
| CN105210151A (en) * | 2013-03-15 | 2015-12-30 | 赛瑞丹公司 | Method of cooling nuclear reactor and nuclear reactor including polyhedral boron hydride or carborane anions |
| CN103310855A (en) * | 2013-05-23 | 2013-09-18 | 中国科学院合肥物质科学研究院 | Liquid heavy metal cooling reactor fuel assembly |
| JP2015059791A (en) * | 2013-09-18 | 2015-03-30 | 株式会社東芝 | Fast reactor core and fast reactor comprising the core |
| RU2014112921A (en) * | 2014-04-02 | 2015-10-10 | Открытое акционерное общество "Центральное конструкторское бюро машиностроения" | FUEL ASSEMBLY |
| KR101549603B1 (en) * | 2015-02-25 | 2015-09-02 | 한국과학기술원 | A passive safety device and a nuclear fuel assembly with the passive safety device |
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| 解家春等: "TOPAZ-Ⅱ反应堆慢化剂温度效应分析", 《原子能科学技术》 * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110853774A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor |
| CN110853774B (en) * | 2019-11-21 | 2021-05-04 | 中国核动力研究设计院 | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor |
| CN111128411A (en) * | 2019-12-31 | 2020-05-08 | 中国科学院合肥物质科学研究院 | Small-size solid state reactor core |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106531232B (en) | 2017-09-22 |
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