CN103474097B - High Fast neutron flux reactor core - Google Patents
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- CN103474097B CN103474097B CN201210182828.4A CN201210182828A CN103474097B CN 103474097 B CN103474097 B CN 103474097B CN 201210182828 A CN201210182828 A CN 201210182828A CN 103474097 B CN103474097 B CN 103474097B
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention belongs to nuclear reactor designs technical field, be specifically related to a kind of high Fast neutron flux reactor core.This reactor core includes fuel assembly, C&P systems and beryllium assembly；Fuel assembly is hexagon thimble tube fuel assembly, and several fuel assemblies compact Layout ringwise has 6 fuel assemblies on innermost layer ring, forms fast neutron trap in the center of its annular region；The outside of adjacent fuel assembly annular region is disposed with several hexagon beryllium assemblies, forms neutron sink；Some C&P systems two row in two rows are spaced in " well " font and are arranged between fuel assembly.High Fast neutron flux reactor core of the present invention, the U-235 enrichment level and the domestic cartridge body that meet world restriction manufacture and the requirement of coolant flow speed design level, Fast neutron flux level in higher irradiation channel can be obtained, strengthen and widen irradiation ability and the range of application of test reactor.
Description
Technical field
The invention belongs to nuclear reactor designs technical field, be specifically related to a kind of high Fast neutron flux reactor core.
Background technology
The development of Nuclear Power Engineering be unable to do without nuclear reactor, and the development of nuclear reactor be unable to do without test reactor.
Test reactor has very important effect to the exploitation of various reactor heap-type.The development trend of modern test reactor
That there is high thermal neutron or Fast neutron flux, the experimental hole that number is many, including a number of greatly
Size duct.The important goal that advanced test reactor design is pursued is high Fast neutron flux.In heap
Fast neutron flux is the highest, and the time required for material irradiation test is the shortest.Such as, fusion reactor
Being one of following most promising energy, its material used needs the strongest radiation-resistant property, it is desirable to reach
Irradiation dose to 150dpa/a.Within the shortest time, to complete the irradiation test of material, need
Possesses the ETR Engineering Test Reactor having high Fast neutron flux test duct.
High Fast neutron flux test reactor needs fuel element to have high fission density, does not the most use round bar shape
Fuel element, generally uses template, sleeve or involute shape fuel element.The Europe that plan is built is first
Enter test reactor JHR heap, use U3Si2-Al cylindrical fuel and Bellis perennis type grid arrangement mode, core body uranium
Density is 4.8gU/cm3, U-235 enrichment is 27%, and its enrichment level is higher than international core industry universal
The test reactor fuel enrichment upper limit 20% that regulation limits.JHR uses " cross Flos Cannabis type fuel pin ",
Arranging 90 fuel pins in one lattice cell, there is diameter 32mm duct at center, places test part." cross
Flos Cannabis type fuel pin " power density in assembly is at a relatively high, and its heat-transfer capability is very poor, therefore " cross fiber crops
Flower pattern fuel pin " do involucrum with zirconium or rustless steel, reactor core wants high pressure, high flow rate could derive heat.JHR
Heap design power is 100MW, active section height 60cm, fuel element coolant flow speed 18m/s.?
Use under the precondition of the 27% enrichment U-235 being higher than international limit value, its fuel assembly mesopore
Maximum Fast neutron flux flux target is 5 × 1014n/cm2/ s (E ＞ 0.907MeV).
In international core industry universal regulation limit assay heap fuel, U-235 enrichment is less than 20%, it addition,
Internal fuel manufacture level requires U3Si2-Al fuel core body uranium density is not higher than 4.0gU/cm3Could be preferably
The uniformity of uranium in ground guarantee core body, in the thimble tube fuel assembly of domestic maturation, coolant flow speed is allowed
Design higher limit be 12m/s.Compared to JHR heap, relatively low U-235 enrichment, fuel core body uranium
Density and coolant flow speed limit core power density and the neutron fluence rate level of domestic test reactor.
Therefore, the U-235 enrichment level limited based on the world and domestic cartridge body manufacture and coolant stream
Speed design level, needs to propose rational reactor core display, it is thus achieved that high Fast neutron flux reactor core, to improve
The material irradiation ability of test reactor.
Summary of the invention
It is an object of the invention to U-235 enrichment level based on world restriction and domestic fuel core body
Manufacture and coolant flow speed design level, on the premise of guarantee safety and structure are feasible, it is provided that Yi Zhonggao
Fast neutron flux reactor core, with Fast neutron flux level in the irradiation channel that acquisition is higher.
For reaching above-mentioned purpose, the technical solution used in the present invention is:
A kind of high Fast neutron flux reactor core, this reactor core includes fuel assembly, C&P systems and beryllium assembly；
Fuel assembly is hexagon thimble tube fuel assembly, and several fuel assemblies compact Layout ringwise is interior
There are 6 fuel assemblies on layer ring, form fast neutron trap in the center of its annular region；Adjacent fuel stack
The outside of part annular region is disposed with several hexagon beryllium assemblies, forms neutron sink；Some controls
Rod assembly two row in two rows are spaced in " well " font and are arranged between fuel assembly.
Described fuel assembly is seven layers of fuel assembly, 42 seven layers fuel assembly compact Layout ringwise,
6 seven layers of fuel assemblies are had on inner layer ring.
Described fuel assembly includes seven layers of fuel assembly and four layers of fuel assembly, 39 seven layers of fuel assemblies and
3 four layers fuel assembly compact Layout ringwise, on innermost layer ring, interval is disposed with 3 seven layers of fuel stack
Part and 3 four layers of fuel assemblies.
Described fast neutron trap is disposed with 1 little irradiation channel.
Described neutron sink is disposed with several big irradiation channels, middle irradiation channel and little irradiation channel.
Being disposed with 1 little irradiation channel in described fast neutron trap, its a diameter of 69mm, in neutron sink
Arrange 2 big irradiation channels, its a diameter of 260mm, 4 middle irradiation channels, its a diameter of 150mm,
2 little irradiation channels, its a diameter of 69mm.
Described seven layers of fuel assembly include aluminum jacket, 7 grate firing material sleeve pipes, coolant water, water squeezing mandrel；
Every grate firing material sleeve pipe is made up of tubular fuel core body and fuel can, and the thickness of fuel core body is 0.6mm,
Outermost layer fuel sleeve pipe periphery is cased with hexagon aluminum jacket, and the center-filled of innermost layer fuel sleeve pipe has water squeezing
Mandrel, water squeezing mandrel is aluminium bar；Aluminum jacket, between each grate firing material sleeve pipe and water squeezing mandrel, it is filled with cooling
Agent water.
Described four layers of fuel assembly include aluminum jacket, 4 grate firing material sleeve pipes, coolant water, water squeezing mandrel and
Inner sleeve；Every grate firing material sleeve pipe is made up of tubular fuel core body and fuel can, and the thickness of fuel core body is
0.6mm, outermost layer fuel sleeve pipe periphery is cased with hexagon aluminum jacket, and the inner side of innermost layer fuel sleeve pipe sets
Being equipped with inner sleeve, the center-filled of inner sleeve has water squeezing mandrel, water squeezing mandrel to be aluminium bar；Aluminum jacket, each
It is filled with coolant water between grate firing material sleeve pipe, inner sleeve and water squeezing mandrel.
Described C&P systems number is 16, point five row's arrangements: wherein first row is from left to right followed successively by
Shim rod E1, shim rod F1；Second row is from left to right followed successively by shim rod D1, safety rod A1, compensate
Rod B1, safety rod A2, regulating rod H；3rd row is from left to right followed successively by shim rod C1, shim rod C2；
4th row is from left to right followed successively by regulating rod G, safety rod A3, shim rod B2, safety rod A4, compensate
Rod D2；5th row is from left to right followed successively by shim rod F2, shim rod E2。
Described 16 C&P systems control rod withdrawal sequences are: first by safety rod A1, safety rod A2, safety rod
A3, safety rod A4Synchronous lifting is to top, more respectively regulating rod H, regulating rod G is risen to reactor core successively
Half height, then by the shim rod F of reactor core periphery1With shim rod F2, shim rod E1With shim rod E2、
Shim rod D1With shim rod D2Divide three groups and rise to top successively, next by the compensation in reactor core centre
Rod B1With shim rod B2, shim rod C1With shim rod C2Two groups are divided to rise to top successively, finally will regulation
Rod G, regulating rod H rise to top successively.
Having the beneficial effect that acquired by the present invention
High Fast neutron flux reactor core of the present invention, meet the world limit U-235 enrichment level and
Domestic cartridge body manufactures and the requirement of coolant flow speed design level, can obtain higher irradiation channel
Interior Fast neutron flux level, strengthens and widens irradiation ability and the range of application of test reactor；
High Fast neutron flux reactor core of the present invention, using core body uranium density is 3.9gU/cm3's
U3Si2-Al fuel, U-235 enrichment is 19.75%, and core coolant flow speed is 12m/s, at reactor core
Under conditions of power density is suitable with JHR heap, in reactor core irradiation channel, average Fast neutron flux is up to about
4.0×1014n/cm2/ s, in irradiation channel central axial 10cm height Fast neutron flux peak value up to
5.0×1014n/cm2/ s, Fast neutron flux level is suitable with JHR heap, far above domestic in-service high pass
Amount ETR Engineering Test Reactor HFETR.The internal irradiation of falling neutron sink duct can also obtain considerable neutron fluence rate
Level, is likewise supplied with higher irradiation ability and practical value；
High Fast neutron flux reactor core of the present invention, peak value Fast neutron flux place irradiation channel straight
Footpath is 69mm, compared to JHR heap fuel median pore diameter 32mm, can put into larger sized test
Part, possesses higher irradiation ability.In addition to above-mentioned irradiation channel, high Fast neutron flux of the present invention
Reactor core is also with the irradiation channel of mesopore 3 a diameter of 25mm of formation of four layers of fuel assembly, can be same
Time place several test part and carry out Irradiation Test；
The present invention uses multilayer sleeve fuel assembly, and uses thicker fuel core body, can improve reactor core merit
Rate density is to obtain higher Fast neutron flux；
The outermost layer fuel sleeve pipe periphery of fuel assembly of the present invention is cased with hexagon aluminum jacket, and at innermost layer
Fuel cannula center fills water squeezing mandrel, to reduce the water yield of fuel region, weakens neutron-absorbing and slowing down,
Improve Fast neutron flux；
The present invention utilizes fuel assembly compact Layout and is arranged in the peripheral beryllium assembly in fuel assembly annulus together
Time form neutron sink and neutron sink, at neutron sink and arrange multiple various sizes of irradiation in neutron sink
Duct, makes reactor core be applicable to different fluence rate requirement, and possesses the ability of irradiation different size material；
In the reactor core that the present invention proposes, C&P systems is arranged along level, vertical direction in " well " font,
Convenient control rod guide tube support of opening on the premise of not dismantling Irradiation Test device, beneficially reactor core maintenance,
The operation such as reload；
The C&P systems control rod withdrawal sequence that the shim rod ecto-entad that the present invention proposes proposes successively, can obtain
Thermal technology's safety requirements is met while obtaining high Fast neutron flux.
Accompanying drawing explanation
Fig. 1 is high Fast neutron flux reactor core example I of the present invention；
Fig. 2 is high Fast neutron flux reactor core Example II of the present invention；
Fig. 3 is seven grate firing material component diagram of high Fast neutron flux reactor core of the present invention；
Fig. 4 is four grate firing material component diagram of high Fast neutron flux reactor core of the present invention；
In figure: 1, cobalt target；2, seven layers of fuel assembly；3, middle irradiation channel；4, C&P systems；5、
Beryllium assembly；6, big irradiation channel；7, little irradiation channel；8, aluminum jacket；9, fuel sleeve pipe；10、
Coolant water；11, water squeezing mandrel；12, shim rod E1；13, shim rod F1；14, shim rod D1；
15, safety rod A1；16, shim rod B1；17, safety rod A2；18, regulating rod H；19, compensate
Rod C1；20, shim rod C2；21, regulating rod G；22, safety rod A3；23, shim rod B2；24、
Safety rod A4；25, shim rod D2；26, shim rod F2；27, shim rod E2；28, four grate firing material
Assembly；29, inner sleeve.
Detailed description of the invention
The present invention is further detailed explanation with embodiment below in conjunction with the accompanying drawings.
Embodiment 1:
As it is shown in figure 1, high Fast neutron flux reactor core of the present invention includes 1, seven layers of fuel stack of cobalt target
Part 2, middle irradiation channel 3, C&P systems 4, beryllium assembly 5, big irradiation channel 6 and little irradiation channel
7；Seven layers of fuel assembly 2 are hexagon thimble tube fuel assembly, and 42 seven layers of fuel assemblies 2 are ringwise
Compact Layout, innermost layer ring has 6 seven layers of fuel assemblies 2, is formed in the center of its annular region
Fast neutron trap, is disposed with 1 little irradiation channel 7 in fast neutron trap, can obtain in little irradiation channel 7
Fast neutron flux that must be higher；The outside of adjacent seven layers of fuel assembly 2 annular region is disposed with several
Hexagon beryllium assembly 5, beryllium assembly 5 is used as moderator and reflecting layer, forms neutron sink；At neutron
Trap is disposed with several big irradiation channels 6, middle irradiation channel 3 and little irradiation channel 7；Adjacent seven grate firings
The outside of material assembly 2 annular region is disposed with cobalt target 1；Some C&P systems 4 two row in two rows in
" well " font interval is arranged between seven layers of fuel assembly 2, opens along level, vertical direction to facilitate
The operations such as control rod guide tube support, beneficially reactor core safeguard, reloads.
Embodiment 2:
As in figure 2 it is shown, high Fast neutron flux reactor core of the present invention includes 1, seven layers of fuel stack of cobalt target
Part 2, middle irradiation channel 3, C&P systems 4, beryllium assembly 5, big irradiation channel 6, little irradiation channel 7
With four layers of fuel assembly 28；Seven layers of fuel assembly 2 and four layers of fuel assembly 28 are hexagon thimble tube
Fuel assembly, 2 and 3 four layers fuel assembly 28 compact Layout ringwise of 39 seven layers of fuel assemblies,
On innermost layer ring, interval is disposed with 2 and 3 four layers of fuel assemblies 28 of 3 seven layers of fuel assemblies, at its ring
The center in shape region forms fast neutron trap, is disposed with 1 little irradiation channel 7 in fast neutron trap,
Little irradiation channel 7 can obtain higher Fast neutron flux；Adjacent seven layers of fuel assembly 2 annular region
Outside be disposed with several hexagon beryllium assemblies 5, beryllium assembly 5 is used as moderator and reflecting layer, is formed
Neutron sink；Several big irradiation channels 6, middle irradiation channel 3 and little spoke it is disposed with in neutron sink
According to duct 7；The outside of adjacent seven layers of fuel assembly 2 annular region is disposed with cobalt target 1；Some control rods
Assembly 4 two row in two rows are spaced in " well " font and are arranged between seven layers of fuel assembly 2, to facilitate edge
Level, vertical direction open control rod guide tube support, beneficially reactor core safeguard, the operation such as reload.
As it is shown on figure 3, seven layers of fuel assembly 2 described in embodiment 1, embodiment 2 include aluminum jacket 8,
7 grate firing material sleeve pipes 9, coolant water 10, water squeezing mandrel 11；Every grate firing material sleeve pipe 9 is by tubular cartridge
Body and fuel can composition, the thickness of fuel core body is 0.4 ~ 0.6mm, preferably 0.6mm, outermost layer
Fuel sleeve pipe 9 periphery is cased with hexagon aluminum jacket 8, and the center-filled of innermost layer fuel sleeve pipe 9 has water squeezing
Mandrel 11, water squeezing mandrel 11 is aluminium bar；Aluminum jacket 8, each grate firing material sleeve pipe 9 and water squeezing mandrel 11 it
Between be filled with coolant water 10；
As shown in Figure 4, described in embodiment 2, four layers of fuel assembly 28 include aluminum jacket 8,4 grate firing material
Sleeve pipe 9, coolant water 10, water squeezing mandrel 11 and inner sleeve 29；Every grate firing material sleeve pipe 9 is fired by tubular
Material core body and fuel can composition, the thickness of fuel core body is 0.4 ~ 0.6mm, preferably 0.6mm,
Outer layer fuel sleeve pipe 9 periphery is cased with hexagon aluminum jacket 8, and the inner side of innermost layer fuel sleeve pipe 9 is provided with
Inner sleeve 29, the center-filled of inner sleeve 29 has water squeezing mandrel 11, water squeezing mandrel 11 to be aluminium bar；Aluminum bag
Shell 8, each grate firing material sleeve pipe 9, between inner sleeve 29 and water squeezing mandrel 11, it is filled with coolant water 10；
In embodiment 2, by extracting the water squeezing mandrel 11 in four layers of fuel assembly 28 out, diameter can be formed
The mesopore of 25mm is used as irradiation channel.
Embodiment 1, embodiment 2 be disposed with in fast neutron trap little irradiation channel 7, its a diameter of 69mm,
2 big irradiation channels 6 of layout in neutron sink, its a diameter of 260mm, 4 middle irradiation channels 3, its
A diameter of 150mm, 2 little irradiation channels 7, its a diameter of 69mm；Cobalt target 1 number is 2；Control
Rod assembly 4 number processed is 16, point five row's arrangements: wherein first row is from left to right followed successively by shim rod
E112, shim rod F113；Second row is from left to right followed successively by shim rod D114, safety rod A115, compensate
Rod B116, safety rod A217, regulating rod H18；3rd row is from left to right followed successively by shim rod C119、
Shim rod C220；4th row is from left to right followed successively by regulating rod G21, safety rod A322, shim rod B223、
Safety rod A424, shim rod D225；5th row is from left to right followed successively by shim rod F226, shim rod E227。
The control rod withdrawal sequence of C&P systems 4 is bigger to Fast neutron flux and core power distribution influence.In order to
Thermal technology's safety requirements, 16 C&P systems 4 control rod withdrawal sequences are met while obtaining high Fast neutron flux
For: first by safety rod A115, safety rod A217, safety rod A322, safety rod A424 Synchronous liftings to top,
The most respectively regulating rod H18, regulating rod G21 are risen to successively reactor core half height, then by reactor core periphery
Shim rod F113 and shim rod F226, shim rod E112 and shim rod E227, shim rod D114 and shim rod
D225 points three groups rise to top, successively next by the shim rod B in reactor core centre116 and shim rod
B223, shim rod C119 and shim rod C220 points two groups rise to top, successively finally by regulating rod G21, tune
Joint rod H18 rises to top successively.
Claims (6)
1. one kind high Fast neutron flux reactor core, it is characterised in that: this reactor core includes fuel assembly, control
Rod assembly (4) and beryllium assembly (5)；Fuel assembly is hexagon thimble tube fuel assembly, several fuel
Assembly compact Layout ringwise, innermost layer ring has 6 fuel assemblies, in the center of its annular region
Form fast neutron trap；The outside of adjacent fuel assembly annular region is disposed with several hexagon beryllium assemblies
(5) neutron sink, is formed；Some C&P systems (4) two row in two rows are spaced in " well " font
It is arranged between fuel assembly；Described fast neutron trap is disposed with 1 little irradiation channel (7), its diameter
For 69mm, neutron sink arranges 2 big irradiation channels (6), its a diameter of 260mm, in 4
Irradiation channel (3), its a diameter of 150mm, 2 little irradiation channels (7), its a diameter of 69mm；
Described C&P systems (4) number is 16, point five row's arrangements: wherein first row is the most successively
For shim rod E1(12), shim rod F1(13)；Second row is from left to right followed successively by shim rod D1(14)、
Safety rod A1(15), shim rod B1(16), safety rod A2And regulating rod H (18) (17)；3rd
Row is from left to right followed successively by shim rod C1(19), shim rod C2(20)；4th row is from left to right followed successively by
Regulating rod G (21), safety rod A3(22), shim rod B2(23), safety rod A4(24) and compensate
Rod D2(25)；5th row is from left to right followed successively by shim rod F2(26), shim rod E2(27)。
High Fast neutron flux reactor core the most according to claim 1, it is characterised in that: described fuel
Assembly is seven layers of fuel assembly (2), 42 seven layers fuel assembly (2) compact Layout ringwise, interior
6 seven layers fuel assembly (2) are had on layer ring.
High Fast neutron flux reactor core the most according to claim 1, it is characterised in that: described fuel
Assembly includes seven layers of fuel assembly (2) and four layers of fuel assembly (28), 39 seven layers fuel assembly (2)
With 3 four layers fuel assembly (28) compact Layout ringwise, on innermost layer ring, interval is disposed with 3 seven
Layer fuel assembly (2) and 3 four layers fuel assembly (28).
4. according to the high Fast neutron flux reactor core described in Claims 2 or 3, it is characterised in that: described
Seven layers of fuel assembly (2) include aluminum jacket (8), 7 grate firings material sleeve pipe (9), coolant water (10) and
Water squeezing mandrel (11)；Every grate firing material sleeve pipe (9) is made up of tubular fuel core body and fuel can, fuel
The thickness of core body is 0.6mm, and outermost layer fuel sleeve pipe (9) periphery is cased with hexagon aluminum jacket (8),
The center-filled of internal layer fuel sleeve pipe (9) has water squeezing mandrel (11), water squeezing mandrel (11) to be aluminium bar；
Aluminum jacket (8), between each grate firing material sleeve pipe (9) and water squeezing mandrel (11), it is filled with coolant water (10).
High Fast neutron flux reactor core the most according to claim 3, it is characterised in that: described four layers
Fuel assembly (28) includes aluminum jacket (8), 4 grate firings material sleeve pipe (9), coolant water (10), water squeezing
Mandrel (11) and inner sleeve (29)；Every grate firing material sleeve pipe (9) is by tubular fuel core body and fuel can
Composition, the thickness of fuel core body is 0.6mm, and outermost layer fuel sleeve pipe (9) periphery is cased with hexagon aluminum bag
Shell (8), the inner side of innermost layer fuel sleeve pipe (9) is provided with inner sleeve (29), inner sleeve (29)
Center-filled has water squeezing mandrel (11), water squeezing mandrel (11) to be aluminium bar；Aluminum jacket (8), each grate firing material
It is filled with coolant water (10) between sleeve pipe (9), inner sleeve (29) and water squeezing mandrel (11).
High Fast neutron flux reactor core the most according to claim 1, it is characterised in that: 16 controls
Rod assembly processed (4) control rod withdrawal sequence is: first by safety rod A1(15), safety rod A2(17), safety rod
A3And safety rod A (22)4(24) Synchronous lifting is to top, more respectively by regulating rod H (18), regulation
Rod G (21) rises to reactor core half height successively, then by the shim rod F of reactor core periphery1(13) and mend
Repay rod F2(26), shim rod E1And shim rod E (12)2(27), shim rod D1(14) and compensate
Rod D2(25) three groups are divided to rise to top successively, next by the shim rod B in reactor core centre1(16)
With shim rod B2(23), shim rod C1And shim rod C (19)2(20) two groups are divided to rise to top successively,
Finally regulating rod G (21), regulating rod H (18) are risen to top successively.
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| CN201210182828.4A CN103474097B (en) | 2012-06-06 | 2012-06-06 | High Fast neutron flux reactor core |
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1132961A (en) * | 1964-11-13 | 1968-11-06 | Atomic Energy Authority Uk | Improvements relating to nuclear reactors |
| FR2517869A1 (en) * | 1981-12-04 | 1983-06-10 | Framatome Sa | COMPLEMENTARY STOP DEVICE FOR SUB-MODERATE NUCLEAR REACTOR |
| CN85109302A (en) * | 1984-11-28 | 1986-08-06 | 株式会社日立制作所 | Light water moderation type nuclear reactor |
| CN101447238A (en) * | 2007-11-27 | 2009-06-03 | 中国核动力研究设计院 | Nuclear reactor core capable of improving neutron flux rate |
| CN101719384A (en) * | 2009-12-03 | 2010-06-02 | 中国核动力研究设计院 | Reactor core of nuclear reactor with fast neutron converting area |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03191897A (en) * | 1989-12-21 | 1991-08-21 | Hitachi Ltd | Core of fast breeder reactor |
| JPH04268489A (en) * | 1991-02-25 | 1992-09-24 | Hitachi Ltd | Core of fast breeder reactor, fuel assembly and control rod assembly to be used and annihilating method for waste of transuranium elements |
| JPH06222176A (en) * | 1993-01-22 | 1994-08-12 | Toshiba Corp | Core of fast reactor |
| JP2002006074A (en) * | 2000-06-20 | 2002-01-09 | Japan Nuclear Cycle Development Inst States Of Projects | Sodium cooling fast reactor |
| JP5302156B2 (en) * | 2009-09-29 | 2013-10-02 | 日立Ｇｅニュークリア・エナジー株式会社 | Fast breeder reactor core |
-
2012
- 2012-06-06 CN CN201210182828.4A patent/CN103474097B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1132961A (en) * | 1964-11-13 | 1968-11-06 | Atomic Energy Authority Uk | Improvements relating to nuclear reactors |
| FR2517869A1 (en) * | 1981-12-04 | 1983-06-10 | Framatome Sa | COMPLEMENTARY STOP DEVICE FOR SUB-MODERATE NUCLEAR REACTOR |
| CN85109302A (en) * | 1984-11-28 | 1986-08-06 | 株式会社日立制作所 | Light water moderation type nuclear reactor |
| CN101447238A (en) * | 2007-11-27 | 2009-06-03 | 中国核动力研究设计院 | Nuclear reactor core capable of improving neutron flux rate |
| CN101719384A (en) * | 2009-12-03 | 2010-06-02 | 中国核动力研究设计院 | Reactor core of nuclear reactor with fast neutron converting area |
Non-Patent Citations (2)
| Title |
|---|
| 5MW低功率反应堆（5MW LPR）;唐学仁等;《核动力工程》;19920831;第13卷(第4期);正文第290-305页 * |
| 高通量工程试验反应堆;徐传效;《核动力工程》;19810831;第2卷(第3期);正文第130-145页 * |
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