CN103093841A - Accelerator driven sub-critical system split type central measuring cylinder system - Google Patents
Accelerator driven sub-critical system split type central measuring cylinder system Download PDFInfo
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- CN103093841A CN103093841A CN2013100130496A CN201310013049A CN103093841A CN 103093841 A CN103093841 A CN 103093841A CN 2013100130496 A CN2013100130496 A CN 2013100130496A CN 201310013049 A CN201310013049 A CN 201310013049A CN 103093841 A CN103093841 A CN 103093841A
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- 230000007246 mechanism Effects 0.000 claims abstract description 32
- 239000000446 fuel Substances 0.000 claims abstract description 13
- 229910052797 bismuth Inorganic materials 0.000 claims abstract description 12
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 claims abstract description 12
- 238000005259 measurement Methods 0.000 claims description 68
- 230000008093 supporting effect Effects 0.000 claims description 15
- 239000007788 liquid Substances 0.000 claims description 14
- 229910001152 Bi alloy Inorganic materials 0.000 claims description 10
- 238000007789 sealing Methods 0.000 claims description 7
- JWVAUCBYEDDGAD-UHFFFAOYSA-N bismuth tin Chemical compound [Sn].[Bi] JWVAUCBYEDDGAD-UHFFFAOYSA-N 0.000 claims description 6
- 230000009257 reactivity Effects 0.000 claims description 5
- 230000002457 bidirectional effect Effects 0.000 claims description 3
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 3
- 238000009434 installation Methods 0.000 claims description 2
- 238000001816 cooling Methods 0.000 abstract description 2
- 238000009377 nuclear transmutation Methods 0.000 abstract 1
- 230000033001 locomotion Effects 0.000 description 6
- 238000000034 method Methods 0.000 description 5
- 239000002699 waste material Substances 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 239000002131 composite material Substances 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 4
- 238000013461 design Methods 0.000 description 3
- 229910001385 heavy metal Inorganic materials 0.000 description 3
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
- 241001057584 Myrrha Species 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000012856 packing Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 229910000909 Lead-bismuth eutectic Inorganic materials 0.000 description 1
- -1 Muscovite BN600 heap Chemical compound 0.000 description 1
- 241000233805 Phoenix Species 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000002144 chemical decomposition reaction Methods 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 239000004020 conductor Substances 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- YGANSGVIUGARFR-UHFFFAOYSA-N dipotassium dioxosilane oxo(oxoalumanyloxy)alumane oxygen(2-) Chemical compound [O--].[K+].[K+].O=[Si]=O.O=[Al]O[Al]=O YGANSGVIUGARFR-UHFFFAOYSA-N 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 229910052627 muscovite Inorganic materials 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 230000009897 systematic effect Effects 0.000 description 1
- 239000013077 target material Substances 0.000 description 1
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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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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides an accelerator driven sub-critical system split type central measuring cylinder system which mainly comprises large and small plugs, a central measuring cylinder main fan-shaped section welded below the large plug, a central measuring cylinder branched fan-shaped section welded below the small plug, a control rod driving mechanism, a proton beam tube, a measuring guide tube, a refueling machine and the like, wherein the large plug is positioned in the center of a system top cover; the small plug is screwed to the large plug and is eccentric to the large plug; the refueling machine is arranged on the small plug and is eccentric to the small plug; and the proton beam tube penetrates through the center of the large plug. During system operation, the lower fan-shaped sections of the large and small plugs are closed to form the central measuring cylinder, the lower fan-shaped section of the small plug rotates during refueling, so that the refueling mechanism enters the system to replace a fuel component. The system mainly aims at an accelerator driven lead bismuth cooling rapid neutron transmutation system, and the problem that the system core refueling is obstructed by the integrated central measuring cylinder is solved.
Description
Technical field
The invention belongs to the active nucleus waste matter processing technology field, be specifically related to a kind of Accelerator Driven Subcritical heap (Accelerator Driven Sub-critical System, ADS) split type center measurement column system relates to Accelerator Driven Subcritical heap center measurement column, cock system and refuelling system.
Background technology
Nuclear waste disposal, especially the final processing of long-life nuke rubbish is a global problem, " separation-transmuting " method is a kind of new way of nuclear waste disposal, namely by Chemical Decomposition, the MA in high-level waste and LLFP are separated, utilize nuclear reaction device (as reactor, accelerator) that the long-life nucleic is transformed into short-lived nuclide or stable nuclide.Accelerator Driven Subcritical system (Accelerator Driven Sub-critical System, ADS) is the ideal device of being devoted at present the transmuting active nucleus waste matter, effectively utilizing nuclear resource and output nuclear energy.International Atomic Energy Agency (IAEA) is listed ADS transmuting heap in novel nuclear power system in, is called " nuclear power system of emerging nuclear waste transmuting and power generation ".
The ADS system is comprised of proton precessional magnetometer, liquid heavy metal spallation target and transmuting nuke rubbish subcritical reactor.The proton beam bombardment heavy metal spallation target part that accelerator produces produces the high energy fast neutron, enters sub-critical reactor in-core transmuting nuke rubbish, produces nuclear fuel and take into account generating.High energy proton is got on heavy metal atom core and is produced spallation reaction, pound the neutron multiplication ratio can reach 30 left and right.Liquid lead bismuth (PbBi) alloy is due to the spallation target material and the cooling medium that have good Multiplication Rate, LMP and higher boiling and good heat-carrying capacity and be chosen as this heap type.Owing to relying on spallation neutron source to drive the transmuting of reactor core nuke rubbish, and be in subcritically, therefore do not have the ability of the self-supporting chain reaction kept, if close accelerator, the neutron in reactor core can be fewer gradually, so this heap has inherent safety features preferably.
Along with the intensification of heap fuel burnup, need to be at certain cycle refuelling assembly.Because the proton tube that produces spallation neutron source is positioned at reactor core central authorities, and can not produce any movement, reactor core top liquid lead bismuth temperature survey conduit, Reactivity and security control rod etc. are arranged in the measurement column of center.The function of center measurement column is to prevent that its inner proton beam tube, control rod guide tube, measuring guide etc. from because the mobile stream that produces of liquid lead bismuth causes vibration, being vitals in heap.If adopt the monoblock type measurement column, pile the fuel assembly because the obstruction of center measurement column and internal part thereof can't be changed, therefore need a kind of novelty of invention center measurement column, coordinate with refuelling system by it, complete New Parent the drawing off of reactor core and irradiated fuel assembly of packing into, and guarantee to reload and do not affect control and measurement to reactor.For the requirement of reloading under this specific condition, be that reactor was unexistent in the past, the problem of reloading of this ADS reactor that is brought by accelerator proton tube, control rod guide tube and temperature survey conduit etc. is needed solution badly.
At present, the fast neutron sub-critical reactor that is used for the nuke rubbish transmuting has the ATW plan of the U.S., the EFIT plan of European Union, the OMEGA plan of Japan, the HAPPY plan of Korea S and the CLEAR-III plan of China.Due to above be all the DEMO Conceptual Design, relevant reactor reloading pattern problem is not all also considered.The cold fast neutron reactor of existing sodium such as Muscovite BN600 heap, BN800 heap, " wind phoenix " heap of France, " Manjusri " heap of Japan and the CEFR heap of China etc., due to reactor core without the accelerator proton tube, control rod drive mechanisms (CRD) is arranged on pet cock, can complete replacing to the reactor fuel assembly by the mobile pet cock of bias when reloading, the rear pet cock that the reloads reactor core concentric position that moves is back guaranteed the control rod drive mechanisms (CRD) function.The cooling fast neutron transmuting heap of the plumbous bismuth of the Accelerator driven of Belgium's design MYRRHA, with CLEAR-I pile structure and functional similarity, be the solution problem of reloading, its design proposal is that reactor core adopts basket-hanging, and the heap bottom reserves a fuel assembly above space (greater than 2 meters) and is used for the refuelling assembly.Inject hundreds of tons of liquid lead bismuths because the space requirement of heap bottom more than 2 meters, if it is feasible adopting forced convection to drive plumbous bismuth mobile, if employing Natural Circulation, increase along with core height, circulation pressure drop increase causes flow velocity to descend or cycle interruption, and the route that reloads from the heap bottom increases and causes the refuelling system complicacy to increase.
Based on above technical background, according to the reloading of CLEAR-I heap, control and measurement demand, special patent of the present invention proposed.
Summary of the invention
Purpose of the present invention: for the reloading of Accelerator Driven Subcritical reactor, control and measurement demand, provide split type center measurement column scheme, the difficult problem that solution is reloaded due to reactor core accelerator proton tube, control rod drive mechanisms (CRD), the set monoblock type center measurement column obstruction of measuring guide, compound motion by large pet cock drives split type center measurement column and moves and form the passage that reloads, and can complete preferably the normal operation that the replacing of reactor fuel assembly is not affected other system.
The technical solution used in the present invention is: a kind of Accelerator Driven Subcritical heap split type center measurement column system, comprise large rotating plug, pet cock, the reactor lid supporting neck, be welded in center measurement column master sector under large rotating plug, be welded in that under pet cock, the center measurement column divides sector, reactor core, seven control rod drive mechanisms (CRD), proton tube, measuring guide on large rotating plug, single control rod drive mechanisms (CRD) and refueling machine on pet cock; Large rotating plug utilizes supporting neck to be arranged on one heart heap top cover center, and is positioned on reactor core; Pet cock is arranged on large rotating plug prejudicially; Refueling machine is arranged on pet cock prejudicially; Proton tube runs through the large rotating plug center, stretches into the reactor core center; Center measurement column master sector and a minute sector are welded in respectively below large rotating plug and pet cock; Single control rod drive mechanisms (CRD) on pet cock is with the common control that realizes Reactivity, security of seven control rod drive mechanisms (CRD) on large rotating plug; The center measurement column is by being welded in center measurement column master sector under large rotating plug, being welded under pet cock the center measurement column divides sector to form, being welded under large rotating plug center measurement column master sector is circumferential 260 ~ 300 degree, being welded under pet cock the center measurement column, to divide sector be circumferential 100 ~ 60 degree, the measuring guide that is positioned at measurement column lower end, center can move up and down, and is used for the location survey sensor; Refuelling system is by the rotation around its geometric center of large rotating plug and pet cock, and the rotation of refueling machine cantilever and moving up and down accurately navigates on any box fuel assembly of reactor core, realizes the installation and removal to fuel assembly.
Wherein, described large rotating plug and pet cock are the cylindrical box structure, can carry out bidirectional rotation around geometric center, large rotating plug is by the supporting of reactor lid supporting neck, and pet cock is supported by large rotating plug, large rotating plug and pet cock top edge arrange sealing device for tin-bismuth alloy, the parts that are used for supporting are provided with ring groove, and filling liquid sn-bi alloy in groove is being supported the corresponding skirtboard of installing on parts, skirtboard inserts ring groove, is immersed in and forms sealing in the liquid tin bismuth alloy.
Wherein, described circumferential 260 ~ 300 degree center measurement column master sectors are welded in the large rotating plug bottom, circumferential 100 ~ 60 degree center measurement columns divide sector to be welded in the pet cock lower end, during the stack operation state, large pet cock lower fan section closed is helped circumferential center measurement column, and measurement column top, center has three row's circular ports circulating with liquid lead bismuth in the assurance post.
Wherein, during described refueling machine reloaded, control rod lifting arm and control rod broke away from, and reserve enough spaces for reloading by carrying on control rod drive mechanisms (CRD) on large rotating plug and single control rod drive mechanisms (CRD).
The present invention compared with prior art beneficial effect is:
(1) reload with the cold fast neutron reactor of existing sodium, control compares with measuring technique, the invention solves because reactor core accelerator proton tube, control rod drive mechanisms (CRD), measuring guide and set center measurement column hinder the technical barrier that reloads and bring, after fuel assembly is changed, can guarantee that proton tube, control rod drive mechanisms (CRD), measuring guide function are unaffected.
(2) reload from heap bottom with MYRRHA and compare, the present invention is by the optimal combination of split type center conductor post, realized reloading from reactor core top, reduced the capacity of the interior plumbous bismuth of heap, good economy performance; In addition, stack height reduces, and has reduced the circulation height of the plumbous bismuth Natural Circulation that is used for discharge reactor core heat, can increase the Natural Circulation flow velocity.
Description of drawings
The split type center of Fig. 1 Accelerator Driven Subcritical heap measurement column system vertical view;
The split type center of Fig. 2 Accelerator Driven Subcritical heap measurement column system front elevation;
The split type center of Fig. 3 Accelerator Driven Subcritical heap measurement column system upward view.
In figure, 1 is large rotating plug, and 2 is pet cock, and 3 is the reactor lid supporting neck, 4 for being welded in center measurement column master sector under large rotating plug, 5 under pet cock, the center measurement column divides sector in order to be welded in, and 6 is reactor core, and 7 is refueling machine, 8 is measuring guide, 9 is proton tube, and 10 is single control rod drive mechanisms (CRD) on pet cock, and 11 is control rod drive mechanisms (CRD) on large rotating plug.
Embodiment
The embodiment of split type center measurement column is described below in conjunction with figure.
As shown in Fig. 1 ~ 3, the split type center of Accelerator Driven Subcritical heap measurement column system, comprise large rotating plug 1, pet cock 2, reactor lid supporting neck 3 is welded in center measurement column master sector 4 under large rotating plug, be welded in that under pet cock, the center measurement column divides sector 5, reactor core 6, seven control rod drive mechanisms (CRD) 11, proton tube 9, measuring guide 8 on large rotating plug, single control rod drive mechanisms (CRD) 10 and refueling machine 7 on pet cock.Large rotating plug 1 is installed on heap top cover center, and pet cock 2 is arranged on large rotating plug 1 prejudicially, and refueling machine 7 eccentric settings are on pet cock 2, and proton tube 9 runs through from the large rotating plug center, extends to reactor core 6 always; Center measurement column master sector 4 and a minute sector 5 are welded in respectively large rotating plug 1 and pet cock 2 belows.Single control rod drive mechanisms (CRD) 10 is set on pet cock 2, forms control to Reactivity, security with seven control rod drive mechanisms (CRD) 11 on large rotating plug 1.Measuring guide 8 is positioned at measurement column lower end, center, is used for the location survey sensor;
Described large rotating plug 1 and pet cock 2 are the cylindrical box structure, can carry out bidirectional rotation around geometric center.Large rotating plug 1 is by 3 supportings of reactor lid supporting neck, and pet cock 2 is by large rotating plug 1 supporting.Large rotating plug 1 and pet cock 2 top edge arrange sealing device for tin-bismuth alloy.The parts that are used for supporting are provided with ring groove, and filling liquid sn-bi alloy in groove is being supported the corresponding skirtboard of installing on parts, and skirtboard inserts ring groove, is immersed in and forms sealing in the liquid tin bismuth alloy;
Described center measurement column is by being welded under large rotating plug circumferential 260 ~ 300 degree of center measurement column master sector 4(), be welded in that under pet cock, the center measurement column divides sector 5(circumferential 100 ~ 60 degree) form.During the stack operation state, large pet cock lower fan section closed is helped circumferential center measurement column, and center measurement column master sector 4 and minute sector 5 tops have three row's circular holes to guarantee circulating of liquid lead bismuth in post;
Described refueling machine refueling machine 7, bias are installed on pet cock 2, and the driving mechanism motor of refueling machine 7 is installed on out-pile, and the refueling machine operating head can be completed and moves up and down and rotate around the spindle;
Described control rod drive mechanisms (CRD) 11 and 10 is by drive motor, and gear train and grabbing device form, and the grabbing device of below can grasp control rod, moves up and down.
During reloading, control rod drive mechanisms (CRD) 11 and 10 breaks away from lifting arm and control rod, is to reload to reserve enough spaces by carrying lifting arm on driving mechanism.Adopt the liquid metal sealing between large rotating plug 1 and pet cock 2 and heap top cover, the heating liquid metal makes it fusing, and large rotating plug 1 and pet cock 2 are rotated.Large rotating plug 1 is positioned to the fuel assembly upper area with the axial rotation of pet cock 2 with refueling machine 7.Refueling machine 7 be arranged on pet cock 2 and with pet cock 2 bias, accurately locate by the arm that reloads of refueling machine 7.When reloading, the pet cock follow procedure rotates, and the center measurement column divides sector 5 to follow pet cock to rotate, and shifts out reactor core 6 tops, makes refueling machine 7 obtain to enter the passage of reactor core 6 central areas, completes the replacing to the reactor fuel assembly; Single control rod is set on pet cock, forms control reactive, security with seven control rods on large rotating plug.
(1) before ADS reactor cold-refueling, close the accelerator shutdown, interrupt the high energy proton bundle and enter spallation target, spallation reaction stops gradually; On control rod drive mechanisms (CRD) 11 and pet cock, single control rod 10 unclamps the control rod assembly of lifting arm lower end clamping and break away from, and makes it be fixed in reactor core 6, and reactivity is implemented to control to guarantee heap safety.
(2) on follow procedure manipulation control rod drive mechanisms (CRD) 11 and pet cock, single control rod 10 will be carried on lifting arm to measurement column upper end, center, and guaranteeing provides enough spaces that reloads for refueling machine 7.
(3) adding the airtight sn-bi alloy of thermal reactor top cover and cock makes it to melt, follow procedure is controlled large pet cock and is turned to the orientation that needs the refuelling assembly, the pet cock eccentric rotary, and its underpart measurement column sector shifts out, refueling machine 7 moves to reactor core top, prepares the refuelling assembly.
(4) weary assembly go out heap: large rotating plug 1 and pet cock 2 composite rotating motions, with the module position that need reload on the refueling machine grip alignment reactor core 6 on refueling machine 7, refueling machine fixture on refueling machine 7 moves downward along guide groove, after refueling machine 7 fixtures pick up weary assembly, move to heap top cover 3 directions along guide groove, through large rotating plug 1 and pet cock 2 composite rotating motions, the refueling machine 7 that clips weary assembly is moved to assembly go out to pile the position again.
(5) New Parent enter heap: the fixture of refueling machine 7 enters position (position that goes out heap with assembly is identical) the gripping New Parent of heap from assembly, composite rotating motion through large rotating plug 1 and pet cock 2, with the position (irradiated fuel assembly draws off) that need reload on the folded assembly alignment reactor core 6 of refueling machine 7, refueling machine 7 fixtures along guide groove to reactor core 6 directions move, with the New Parent reactor core 6 of packing into, the composite rotating motion again of large rotating plug 1 and pet cock 2 moves on to refueling machine 7 the front position of reloading.
(6) large pet cock turns to the front position of reloading, then the eccentric rotary pet cock, makes its lower center measurement column sector and large rotating plug center measurement column sector closure, forms all-round to the center measurement column.
(7) on control rod drive mechanisms (CRD) 3 and pet cock, single control rod 4 lifting arms descend, and make the interior rod assembly of controlling of fixture clamping heap of lower end, complete the replacing of fuel assembly.
The plumbous bismuth cooled reactor center measurement column systematic research of relevant Accelerator driven is fewer in the world at present, and split type center measurement column yet there are no report.
Claims (4)
1. the split type center of Accelerator Driven Subcritical heap measurement column system, it is characterized in that, comprise large rotating plug (1), pet cock (2), reactor lid supporting neck (3) is welded in center measurement column master sector (4) under large rotating plug, be welded in that under pet cock, the center measurement column divides sector (5), reactor core (6), seven control rod drive mechanisms (CRD) (11), proton tube (9), measuring guide (8) on large rotating plug, single control rod drive mechanisms (CRD) (10) and refueling machine (7) on pet cock; Large rotating plug (1) utilizes supporting neck (3) to be arranged on one heart heap top cover center, and is positioned at reactor core (6) top; Pet cock (2) is arranged on large rotating plug (1) prejudicially; Refueling machine (7) is arranged on pet cock (2) prejudicially; Proton tube (9) runs through large rotating plug (1) center, stretches into reactor core (6) center; Center measurement column master sector (4) and a minute sector (5) are welded in respectively below large rotating plug (1) and pet cock (2); The upper single control rod drive mechanisms (CRD) (10) of pet cock (2) is with the common control that realizes Reactivity, security of seven control rod drive mechanisms (CRD) (11) on large rotating plug; The center measurement column comprises and is welded in center measurement column master sector (4) under large rotating plug, and it is circumferentially 260 ~ 300 degree, is welded in that under pet cock, the center measurement column divides sector (5), and it is circumferentially 100 ~ 60 degree; The measuring guide (8) that is positioned at measurement column lower end, center can move up and down, and is used for the location survey sensor; Refuelling system is by the rotation around its geometric center of large rotating plug (1) and pet cock (2), and the rotation of refueling machine (7) cantilever and moving up and down accurately navigates on any box fuel assembly of reactor core the installation and removal of realization to fuel assembly.
2. the split type center of Accelerator Driven Subcritical according to claim 1 heap measurement column system, it is characterized in that: described large rotating plug (1) and pet cock (2) are the cylindrical box structure, can carry out bidirectional rotation around geometric center, large rotating plug (1) is supported by reactor lid supporting neck (3), pet cock (2) is supported by large rotating plug (1), large rotating plug (1) and pet cock (2) top edge arrange the liquid metal sealing device for tin-bismuth alloy, the parts that are used for supporting are provided with ring groove, filling liquid sn-bi alloy in groove, be supported the corresponding skirtboard of installing on parts, skirtboard inserts ring groove, be immersed in and form sealing in the liquid tin bismuth alloy.
3. the split type center of Accelerator Driven Subcritical according to claim 1 heap measurement column system, it is characterized in that: described circumferential 260 ~ 300 degree center measurement column master sectors (4) are welded in the large rotating plug bottom, circumferential 100 ~ 60 degree center measurement columns divide sector (5) to be welded in the pet cock lower end, during the stack operation state, large pet cock lower fan section closed is helped circumferential center measurement column, and measurement column top, center has three row's circular ports (12) circulating with liquid lead bismuth in the assurance post.
4. the split type center of Accelerator Driven Subcritical according to claim 1 heap measurement column system, it is characterized in that: during described refueling machine (7) reloads, control rod lifting arm and control rod break away from, and reserve enough spaces for reloading by carrying on control rod drive mechanisms (CRD) on large rotating plug (11) and single control rod drive mechanisms (CRD) (10).
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| CN104036834A (en) * | 2014-06-20 | 2014-09-10 | 中国科学院合肥物质科学研究院 | Method for measuring subcriticality of subcritical 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 |
| CN104269197A (en) * | 2014-09-27 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Verification device for in-pile refueling system in liquid-state heavy metal reactor |
| CN106601312A (en) * | 2017-01-19 | 2017-04-26 | 清华大学天津高端装备研究院 | ADS (accelerator driven sub-critical system) integrated reactor top structure and nuclear power generation equipment |
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| CN108364699A (en) * | 2018-04-13 | 2018-08-03 | 中广核研究院有限公司 | A kind of reactor pressure vessel for coolant metal fast reactor |
| CN108648840A (en) * | 2018-06-11 | 2018-10-12 | 中广核研究院有限公司 | Device for reactor fuel assemblies handling |
| CN110189835A (en) * | 2019-04-22 | 2019-08-30 | 中广核研究院有限公司 | Reactor core and assembly type core plate structure |
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| CN104036834A (en) * | 2014-06-20 | 2014-09-10 | 中国科学院合肥物质科学研究院 | Method for measuring subcriticality of subcritical 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 |
| CN104167226B (en) * | 2014-09-05 | 2017-01-25 | 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 |
| CN104269197A (en) * | 2014-09-27 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Verification device for in-pile refueling system in liquid-state heavy metal reactor |
| CN104269197B (en) * | 2014-09-27 | 2016-08-24 | 中国科学院合肥物质科学研究院 | The checking device of a kind of refuelling system in liquid heavy metal reactor and method of work thereof |
| CN106601309A (en) * | 2016-12-30 | 2017-04-26 | 中国科学院合肥物质科学研究院 | Non-penetration spallation target and reactor coupling system |
| CN106601312A (en) * | 2017-01-19 | 2017-04-26 | 清华大学天津高端装备研究院 | ADS (accelerator driven sub-critical system) integrated reactor top structure and nuclear power generation equipment |
| CN107154277A (en) * | 2017-06-05 | 2017-09-12 | 中国科学院近代物理研究所 | Refuelling system and the Accelerator Driven Subcritical reactor with the refuelling system |
| CN108364699A (en) * | 2018-04-13 | 2018-08-03 | 中广核研究院有限公司 | A kind of reactor pressure vessel for coolant metal fast reactor |
| CN108364699B (en) * | 2018-04-13 | 2024-05-17 | 中广核研究院有限公司 | Reactor pressure vessel for metal coolant fast reactor |
| CN108648840A (en) * | 2018-06-11 | 2018-10-12 | 中广核研究院有限公司 | Device for reactor fuel assemblies handling |
| CN108648840B (en) * | 2018-06-11 | 2024-01-23 | 中广核研究院有限公司 | Device for loading and unloading fuel assembly of reactor |
| CN110189835A (en) * | 2019-04-22 | 2019-08-30 | 中广核研究院有限公司 | Reactor core and assembly type core plate structure |
| CN110189835B (en) * | 2019-04-22 | 2020-12-04 | 中广核研究院有限公司 | Reactor core and assembled reactor core plate structure |
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