CN208225535U - Molten salt reactor reactor core, fused salt shut-down system and fuel circulating system - Google Patents
Molten salt reactor reactor core, fused salt shut-down system and fuel circulating system Download PDFInfo
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- CN208225535U CN208225535U CN201820215685.5U CN201820215685U CN208225535U CN 208225535 U CN208225535 U CN 208225535U CN 201820215685 U CN201820215685 U CN 201820215685U CN 208225535 U CN208225535 U CN 208225535U
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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
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Abstract
The utility model discloses a kind of molten salt reactor reactor core, fused salt shut-down system and fuel circulating system.The active region of the molten salt reactor reactor core has transmuting area independent and breeding blanket, and the transmuting area is set in the breeding blanket；The resulting great number residue neutron of transmuting in villaumite and fast spectrum transmuting under conditions of without moderator and is transferred to the breeding blanket for higher chain product by the transmuting area；Superthermal spectrum proliferation of the breeding blanket for nuclear fuel thorium under conditions of villiaumite and moderator are graphite nodule.The molten salt reactor reactor core, fused salt shut-down system and fuel circulating system, with excellent thorium uranium proliferative capacity and transmuting ability, TRU that can efficiently in transmuting spentnuclear fuel, and can make full use of nuclear fuel thorium successfully solves the problems, such as the shortage of nuclear fuel resources existing for current nuclear power development and high puts waste from stacking.
Description
Technical field
The utility model relates to a kind of molten salt reactor reactor core, fused salt shut-down system and fuel circulating systems.
Background technique
The nuclear power energy high as a kind of cleaning, low-carbon, energy density, with the advantage that other energy are incomparable.Mesh
Preceding China's nuclear power unit, using the unique existing easily fissioner U-235 of nature as igniter fuel, is adopted based on presurized water reactor
With fuel recycle mode is once passed through, still contain U-235, the U- not fissioned in the spentnuclear fuel that this fuel recycle mode obtains
238, higher chain product (Transuranic, hereinafter referred to as " TRU ") and high radioactivity fission product, and the prior art is not to this
Spentnuclear fuel is post-processed, but is directly stored or buried.Therefore, there is uranium ore demands for the fuel recycle mode
High, nuclear fuel utilization is lowly and its high radioactivity spentnuclear fuel accumulates brought nuclear waste management problem.Wherein, TRU has
Therefore long-term, if do not disposed properly, it will earth environment and biosphere are seriously affected, to the mankind and other lifes
The existence of object constitutes a threat to, and seriously restricts the development of China's Nuclear Power Industry.
In addition, China's uranium reserve is deficient, and thorium reserves enrich (3~4 times) more than uranium, and economy is higher than uranium, while can
Reduce the pollution to environment.If can be made full use of to thorium resources, the development of China's Nuclear Power Industry can be brought favorably
It influences.
However, in the prior art, still lack it is a set of not only can TRU efficiently in transmuting presurized water reactor spentnuclear fuel again can be sharp
With the molten salt reactor reactor core and fused salt shut-down system of nuclear fuel thorium.For the national conditions of China's depleted uranium richness thorium, exploitation is a set of both can be with transmuting
TRU in presurized water reactor spentnuclear fuel, it can use the molten salt reactor reactor core of nuclear fuel thorium again and fused salt shut-down system is need solve at present
The technical issues of.It is therefore opened in addition, still lacking a set of coupling TRU transmuting in the prior art with the fuel circulating system that thorium utilizes
Sending out corresponding fuel circulating system a set of is also the technical issues of need solving at present.
Utility model content
Technical problem to be solved in the utility model be in order to overcome still lack in the prior art it is a set of both can be with transmuting
TRU in presurized water reactor spentnuclear fuel, the molten salt reactor reactor core and fused salt shut-down system of nuclear fuel thorium be can use again, and provided a kind of novel
Molten salt reactor reactor core, fused salt shut-down system and fuel circulating system.The molten salt reactor reactor core, fused salt shut-down system and fuel circulating system,
With excellent thorium uranium proliferative capacity and transmuting ability, TRU that can efficiently in transmuting spentnuclear fuel, and nuclear fuel can be made full use of
Thorium successfully solves the problems, such as that waste from stacking is put in the shortage of nuclear fuel resources existing for current nuclear power development and height.
The utility model solves above-mentioned technical problem by the following technical programs:
The utility model provides a kind of molten salt reactor reactor core, and the active region of the molten salt reactor reactor core has transmuting independent
Area and breeding blanket, and the transmuting area is set in the breeding blanket；
The transmuting area is for higher chain product in villaumite and fast spectrum transmuting under conditions of without moderator and will be obtained by transmuting
Great number residue neutron be transferred to the breeding blanket；
Superthermal spectrum proliferation of the breeding blanket for nuclear fuel thorium under conditions of villiaumite and moderator are graphite nodule.
In the utility model, graphite reflector is routinely equipped with by this field outside the active region.
In the utility model, the fast spectrum refers to that neutron energy is greater than or equal to the neutron energy spectrum of 0.5MeV.
In the utility model, the superthermal spectrum refers to that neutron energy is the neutron energy spectrum of 1eV-0.5MeV.
In the utility model, preferably, the transmuting area and the breeding blanket are coaxially disposed.
In the utility model, the transmuting area routinely referred to by this field in molten salt reactor reactor core for the transmuting
Space.
In the utility model, the transmuting area is routinely equipped with material-feeding port by this field, and the material-feeding port to described for transmuting
Become area and supplements the villaumite containing higher chain product.
In the utility model, the breeding blanket routinely referred to by this field in molten salt reactor reactor core for the proliferation
Space.
In the utility model, preferably, the fused salt volume in the transmuting area is the fused salt total volume in the active region
0.4-0.7 times.More preferably, the fused salt volume in the transmuting area is 0.5 times of the fused salt total volume in the active region.This
Place is it should be noted that the fused salt total volume in the active region refers to fused salt volume and the proliferation in the transmuting area
The summation of fused salt volume in area.
In the utility model, preferably, the volume of the graphite nodule in the breeding blanket accounts for the total volume of the breeding blanket
58%-62% may be, for example, 60%.
In the utility model, preferably, the top of the breeding blanket is equipped with graphite nodule entrance, the bottom of the breeding blanket is set
There is graphite nodule outlet, the graphite nodule entrance for providing graphite nodule to the breeding blanket when reloading, use by the graphite nodule outlet
The graphite nodule of the breeding blanket is discharged when reloading.The technical solution can replace all slowing downs in the case where not shutdown
Agent graphite nodule, is of great significance in industrial application.
The utility model also provides a kind of fused salt shut-down system, and the fused salt shut-down system includes molten salt reactor reactor core above-mentioned, institute
It states transmuting area and recycles external loop equipped with villaumite, and the transmuting area collectively forms villaumite with villaumite circulation external loop and is recycled back to
Road；It is successively arranged First Heat Exchanger and fission product post-processing unit along villaumite flow direction on the villaumite circulation external loop,
The First Heat Exchanger is used to remove the heat in villaumite, and the fission product post-processing unit is used to remove the fission in villaumite
Product；The breeding blanket is equipped with villiaumite and recycles external loop, and the breeding blanket and villiaumite circulation external loop collectively form villiaumite
Circulation loop；The second heat exchanger and extractor are successively arranged along villiaumite flow direction on villiaumite circulation external loop, described the
Two heat exchangers are used to remove the heat in villiaumite, and the extractor is used for the Pa-233 crude product being obtained by extraction in villiaumite.
In the utility model, sometimes, due to the fission product post-processing unit and the processing energy of the extractor
Power is limited, at this point, the fission product post-processing unit is in parallel with one first pipeline, the extractor and one second pipeline are simultaneously
Connection.In above-mentioned technical proposal, the villaumite after exchanging heat is divided into two strands, returns to transmuting area after one is purified, it is remaining one without
Purification directly returns to transmuting area；Villiaumite after exchanging heat is divided into two strands, returns to breeding blanket after stock-traders' know-how extraction, it is remaining one without
Extraction directly returns to breeding blanket.
In the utility model, the First Heat Exchanger can also be connected with steam generator and generating set.
The utility model also provides a kind of fuel circulating system, the fuel circulating system include spentnuclear fuel generate unit,
Solid fuel post-processing unit, fused salt shut-down system above-mentioned, decay tank, nuclear fuel manufacture room, small modular molten salt reactor and liquid
State fuel post-processing unit；Wherein,
The spentnuclear fuel generates unit and post-processes for generating spentnuclear fuel and sending the spentnuclear fuel to the solid fuel
Unit；
The solid fuel post-processing unit is used for the transuranium that will be generated in the spentnuclear fuel that unit is sent from the spentnuclear fuel
Nucleic extracts and send the higher chain product extracted to the transmuting area；
The extractor is also used to send the Pa-233 crude product to the decay tank；
The decay tank is used to the Pa-233 in the Pa-233 crude product decaying into U-233, and by gained U-233 crude product
Fluorination separation, and obtain U-233 sterling；
Nuclear fuel manufacture room is used for the U-233 sterling and be made the small modular molten salt reactor open heap combustion
Material, and send the reactor core to the small modular molten salt reactor as reactor fuel the heap fuel that opens；
The small modular molten salt reactor is used for the burning of the reactor fuel, and will burn gained spentnuclear fuel and send to liquid
Fuel post-processing unit；
The liquid fuel post-processing unit is used for the higher chain product in the spentnuclear fuel of the small modular molten salt reactor
It extracts and send the higher chain product extracted to the transmuting area of the fused salt shut-down system.
In the utility model, preferably, it is presurized water reactor that the spentnuclear fuel, which generates unit,.
Without prejudice to the field on the basis of common sense, above-mentioned each optimum condition, can any combination it is each to get the utility model
Preferred embodiments.
In the utility model, the agents useful for same and raw material in addition to spentnuclear fuel are commercially available.
The positive effect of the utility model is: the utility model provides a kind of molten salt reactor reactor core, fused salt shut-down system
And fuel circulating system.The molten salt reactor reactor core, fused salt shut-down system and fuel circulating system, with excellent thorium uranium proliferative capacity and
Transmuting ability, TRU that can efficiently in transmuting spentnuclear fuel, and nuclear fuel thorium can be made full use of, successfully solve current nuclear power development
Existing nuclear fuel resources shortage and the high problem for putting waste from stacking.
Detailed description of the invention
Fig. 1 is the top view of the molten salt reactor of embodiment 1.
Fig. 2 is the structural schematic diagram of the fused salt shut-down system of embodiment 1.
Fig. 3 is the schematic diagram of the fuel circulating system of embodiment 1.
Description of symbols:
Transmuting area 10
20 graphite nodule entrance of breeding blanket, 21 graphite nodule outlet 22
Graphite reflector 30
Villaumite recycles external loop 40
First Heat Exchanger 50
Fission product post-processing unit 60
Villiaumite recycles external loop 70
Second heat exchanger 80
Extractor 90
First pipeline 100
Second pipeline 110
Specific embodiment
The utility model is further illustrated below by the mode of embodiment, but is not therefore limited in the utility model
Among the embodiment described range.In the following examples, the experimental methods for specific conditions are not specified, according to conventional methods and conditions,
Or it is selected according to product manual.
In following embodiments, fast spectrum refers to that neutron energy is greater than or equal to the neutron energy spectrum of 0.5MeV；During superthermal spectrum refers to
Sub- energy is the neutron energy spectrum of 1eV-0.5MeV.
In following embodiments, transmuting area is routinely referred to the space for transmuting in molten salt reactor reactor core by this field；Increase
Grow area routinely referred to by this field in molten salt reactor reactor core for proliferation space；Fused salt total volume in active region refers to
The summation of the fused salt volume in fused salt volume and breeding blanket in transmuting area.
Embodiment 1
One, molten salt reactor reactor core
Molten salt reactor as shown in Figure 1, the molten salt reactor have molten salt reactor reactor core, and the active region of molten salt reactor reactor core has respectively solely
Vertical transmuting area 10 and breeding blanket 20, and transmuting area 10 is set in breeding blanket 20；Transmuting area 10 for higher chain product in villaumite and
The resulting great number residue neutron of transmuting is simultaneously transferred to breeding blanket 20 by fast spectrum transmuting under conditions of no moderator；Breeding blanket 20
For superthermal spectrum proliferation of nuclear fuel thorium under conditions of villiaumite and moderator are graphite nodule.
Wherein, active region is externally provided with graphite reflector 30.
Wherein, transmuting area 10 and breeding blanket 20 are coaxially disposed.
Wherein, transmuting area 10 is equipped with material-feeding port, and material-feeding port is used to supplement the villaumite containing higher chain product to transmuting area 10.
Wherein, the fused salt volume in transmuting area 10 is 0.5 times of the fused salt total volume in active region, molten in breeding blanket 20
Salt volume is 0.5 times of the fused salt total volume in active region, and the fused salt total volume in active region is 20m3, stone in breeding blanket 20
The volume of tampon accounts for the 60% of the total volume of breeding blanket 20.
Wherein, the top of breeding blanket 20 is equipped with graphite nodule entrance 21, and the bottom of breeding blanket 20 is equipped with graphite nodule outlet 22, stone
Tampon entrance 21 is for providing graphite nodule to breeding blanket 20 when reloading, by breeding blanket 20 when graphite nodule outlet 22 is used to reload
Graphite nodule discharge.
Two, fused salt shut-down system
Fused salt shut-down system as shown in Figure 2, fused salt shut-down system include the molten salt reactor with above-mentioned molten salt reactor reactor core, transmuting area
10, which are equipped with villaumite, recycles external loop 40, and transmuting area 10 and villaumite circulation external loop 40 collectively form villaumite circulation loop；Villaumite
It is successively arranged First Heat Exchanger 50 and fission product post-processing unit 60 along villaumite flow direction on circulation external loop 40, first changes
Hot device 50 is used to remove the heat in villaumite, and fission product post-processing unit 60 is used to remove the fission product in villaumite；Proliferation
Area 20 is equipped with villiaumite and recycles external loop 70, and breeding blanket 20 and villiaumite circulation external loop 70 collectively form villiaumite circulation loop；Villiaumite
It is successively arranged the second heat exchanger 80 and extractor 90 along villiaumite flow direction on circulation external loop 70, the second heat exchanger 80 is used for
The heat in villiaumite is removed, extractor 90 is used for the Pa-233 crude product being obtained by extraction in villiaumite.Wherein, fission product post-processing is single
Member 60 is in parallel with the first pipeline 100, and extractor 90 is in parallel with the second pipeline 110.That is, the villaumite after exchanging heat is divided into two strands,
Transmuting area 10, one remaining not purified directly return transmuting area 10 are returned to after one is purified；Villiaumite after exchanging heat is divided into
Two strands, return to breeding blanket 20 after stock-traders' know-how extraction, it is remaining one without extraction directly return breeding blanket 20.
Wherein, the total thermal power of the fused salt shut-down system is 2250MWth, and thermal conversion efficiency 44.4%, electrical power is
1000MWe, energy are mainly generated by transmuting area 10, and 10 power density of transmuting area is about 200MW/m3。
Three, fuel circulating system
Fuel circulating system as shown in Figure 3 includes that spentnuclear fuel generates unit, solid fuel post-processing unit, above-mentioned fused salt
Shut-down system, decay tank, nuclear fuel manufacture room, small modular molten salt reactor and liquid fuel post-processing unit.Wherein,
Spentnuclear fuel generates unit for generating spentnuclear fuel and sending spentnuclear fuel to solid fuel post-processing unit, and weary combustion
It is presurized water reactor that material, which generates unit,；
Solid fuel post-processing unit is used to extract the higher chain product generated from spentnuclear fuel in the spentnuclear fuel that unit is sent
It send out and by the higher chain product of extraction process through villaumite fuel inlet to transmuting area 10；
Extractor 90 is also used to send Pa-233 crude product to decay tank；
Decay tank is used to decay into the Pa-233 in Pa-233 crude product U-233, and the fluorination of gained U-233 crude product is divided
From, and obtain U-233 sterling；
Nuclear fuel manufacture room is used for U-233 sterling and be made small modular molten salt reactor open heap fuel, and will open heap
Fuel is sent to the reactor core of small modular molten salt reactor as reactor fuel, and it is 0.06kg which, which produces TRU per year,；
Small modular molten salt reactor is used for the burning of reactor fuel, and will burn gained spentnuclear fuel and send to liquid fuel
Manage unit；
Liquid fuel post-processing unit for the higher chain product in the spentnuclear fuel of small modular molten salt reactor is extracted,
And the higher chain product extracted is sent to the transmuting area 10 of fused salt shut-down system.
Application Example 1
The fuel recycle method carried out using above-mentioned fuel circulating system, the fuel recycle method are included the following steps:
(1) villaumite fuel is made after extracting the higher chain product in the spentnuclear fuel of spentnuclear fuel generation unit generation to provide
To transmuting area 10；
(2) higher chain product carries out in villaumite and under conditions of without moderator fast spectrum transmuting, obtains great number residue neutron, great number is surplus
Remaining neutron is transferred to breeding blanket 20；During transmuting, villaumite is flowed around villaumite circulation loop always；
(3) the nuclear fuel thorium in breeding blanket 20 absorbs great number residue neutron under conditions of villiaumite and moderator are graphite nodule
After carry out superthermal spectrum proliferation；During proliferation, villiaumite is flowed around villiaumite circulation loop always；Villiaumite is flowing through extractor 90
When, the Pa-233 in villiaumite obtains Pa-233 crude product after the extractant Bi- Li extraction in extractor 90；
(4) Pa-233 in Pa-233 crude product decays to obtain U-233 crude product, and perfluorinated separation in decay tank, obtains U-233
Sterling；
(5) U-233 sterling is made into 71.7mol%LiF-16mol%BeF in nuclear fuel manufacture room2- 12mol%ThF4-
0.3mol%U-233F4Open heap fuel, open heap fuel and be sent to the reactor core to small modular molten salt reactor as reactor fuel；
(6) reactor fuel obtains spentnuclear fuel, after spentnuclear fuel is sent to liquid fuel after the burning of small modular molten salt reactor
Manage unit；
(7) liquid fuel post-processing unit the higher chain product in the spentnuclear fuel of small modular molten salt reactor is extracted,
And the higher chain product extracted is sent to the transmuting area 10 of fused salt shut-down system.
In step (1), villaumite fuel is by 45mol%HMCl3It is formed with the fused salt of 55mol%NaCl, wherein HM is pressure water
The TRU (MA+Pu) obtained after the post-processing of heap spentnuclear fuel, specific ingredient are Np- 237, Pu-238, Pu-239, Pu-240, Pu-
241, Pu-242, Am-241, Am-243, Cm-244, Cm-245, molar fraction shared by these nucleic is respectively as follows: 20.5%,
8.68%, 11.0%, 17.4%, 10.3%, 11.8%, 11.0%, 6.23%, 2.68%, 0.331%.
In step (2), great number residue neutron be transmuting operation power be 100MWt/m3It is obtained under conditions of above
, First Heat Exchanger 50 is also connected with steam generator and generating set, and the cold fluid of First Heat Exchanger 50 is 92mol%
NaBeF4+ 8mol%NaF.Fission product post-processing unit 60 is blasted, is evaporated under reduced pressure using He bubble, the methods of electrolytic deposition exists
Line removes fission product, while being changed according to pile reactivity, and the villaumite containing TRU is added to make up reactivity toward transmuting area 10
Loss.
In step (3), the villiaumite composition in breeding blanket 20 containing thorium is as follows: 77.5mol%LiF and 22.5mol%
ThF；Coolant in second heat exchanger 80 is FNaBe fused salt.
Effect data:
1, the transmuting rate of TRU is about 80%, TRU transmuting amount up to 750kg.
Due to 25 tons of the annual discharging of 1 million kilowatt presurized water reactor, wherein TRU accounts for 1%, and quality is about 250kg, therefore,
The fused salt shut-down system every year can the TRU that is unloaded of 3 million kilowatt presurized water reactors of transmuting.
2, the fused salt shut-down system thorium uranium breeding ratio is 1.06, can be proliferated 50kg U-233 every year, can start within 6 years a hot merit
The small modular molten salt reactor that rate is 500MW (its U-233 initial load is 303kg).
3, it is 0.06kg that the small modular molten salt reactor, which produces TRU per year, thus the fused salt shut-down system can sufficiently transmuting from small-sized
The TRU that modularization molten salt reactor generates.
Claims (10)
1. a kind of molten salt reactor reactor core, which is characterized in that the active region of the molten salt reactor reactor core have transmuting area independent and
Breeding blanket, and the transmuting area is set in the breeding blanket；
The transmuting area is for higher chain product in villaumite and fast spectrum transmuting under conditions of without moderator and by the resulting height of transmuting
Volume residue neutron is transferred to the breeding blanket；
Superthermal spectrum proliferation of the breeding blanket for nuclear fuel thorium under conditions of villiaumite and moderator are graphite nodule.
2. molten salt reactor reactor core as described in claim 1, which is characterized in that the transmuting area and the breeding blanket are coaxially disposed.
3. molten salt reactor reactor core as described in claim 1, which is characterized in that the fused salt volume in the transmuting area is the activity
0.4-0.7 times of fused salt total volume in area.
4. molten salt reactor reactor core as claimed in claim 3, which is characterized in that the fused salt volume in the transmuting area is the activity
0.5 times of fused salt total volume in area.
5. molten salt reactor reactor core as described in claim 1, which is characterized in that the volume of the graphite nodule in the breeding blanket accounts for described
The 58%-62% of the total volume of breeding blanket.
6. molten salt reactor reactor core as claimed in claim 5, which is characterized in that the volume of the graphite nodule in the breeding blanket accounts for described
The 60% of the total volume of breeding blanket.
7. molten salt reactor reactor core as described in claim 1, which is characterized in that the top of the breeding blanket is equipped with graphite nodule entrance,
The bottom of the breeding blanket is exported equipped with graphite nodule, and the graphite nodule entrance is for providing graphite to the breeding blanket when reloading
The graphite nodule of the breeding blanket is discharged when the graphite nodule outlet is for reloading for ball.
8. a kind of fused salt shut-down system, which is characterized in that the fused salt shut-down system includes as claim 1-7 is described in any item molten
Salt heap reactor core, the transmuting area is equipped with villaumite and recycles external loop, and the transmuting area and the villaumite recycle the common structure of external loop
At villaumite circulation loop；First Heat Exchanger and fission product are successively arranged along villaumite flow direction on the villaumite circulation external loop
Post-processing unit, the First Heat Exchanger are used to remove the heat in villaumite, and the fission product post-processing unit is for removing
Fission product in villaumite；The breeding blanket is equipped with villiaumite and recycles external loop, and the breeding blanket and the villiaumite recycle external loop
Collectively form villiaumite circulation loop；The second heat exchanger and extraction are successively arranged along villiaumite flow direction on the villiaumite circulation external loop
Device is taken, second heat exchanger is used to remove the heat in villiaumite, and the extractor is used for the Pa-233 being obtained by extraction in villiaumite
Crude product.
9. a kind of fuel circulating system, which is characterized in that the fuel circulating system includes that spentnuclear fuel generates unit, solid fuel
Post-processing unit, fused salt shut-down system as claimed in claim 8, decay tank, nuclear fuel manufacture room, small modular molten salt reactor and
Liquid fuel post-processing unit；Wherein,
The spentnuclear fuel generates unit and post-processes list for generating spentnuclear fuel and sending the spentnuclear fuel to the solid fuel
Member；
The solid fuel post-processing unit is used for the higher chain product that will be generated in the spentnuclear fuel that unit is sent from the spentnuclear fuel
It extracts and send the higher chain product extracted to the transmuting area；
The extractor is also used to send the Pa-233 crude product to the decay tank；
The decay tank is used to decay into the Pa-233 in the Pa-233 crude product U-233, and gained U-233 crude product is fluorinated
Separation, and obtain U-233 sterling；
Nuclear fuel manufacture room is used for the U-233 sterling and be made the small modular molten salt reactor open heap fuel,
And send the reactor core to the small modular molten salt reactor as reactor fuel the heap fuel that opens；
The small modular molten salt reactor is used for the burning of the reactor fuel, and will burn gained spentnuclear fuel and send to liquid fuel
Post-processing unit；
The liquid fuel post-processing unit is used to extract the higher chain product in the spentnuclear fuel of the small modular molten salt reactor
It send out and by the higher chain product extracted to the transmuting area of the fused salt shut-down system.
10. fuel circulating system as claimed in claim 9, which is characterized in that it is presurized water reactor that the spentnuclear fuel, which generates unit,.
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110364273A (en) * | 2019-07-10 | 2019-10-22 | 华南理工大学 | A kind of liquid fuel space heap |
| CN111627572A (en) * | 2020-06-04 | 2020-09-04 | 中国科学院上海应用物理研究所 | Modularized molten salt reactor core and molten salt reactor |
| CN111627569A (en) * | 2020-05-14 | 2020-09-04 | 中国科学院上海应用物理研究所 | Transuranic fuel and preparation method and transmutation method thereof |
| CN113744907A (en) * | 2020-05-28 | 2021-12-03 | 哈尔滨工程大学 | Molten salt fuel self-sustaining updating module device |
-
2018
- 2018-02-07 CN CN201820215685.5U patent/CN208225535U/en active Active
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110364273A (en) * | 2019-07-10 | 2019-10-22 | 华南理工大学 | A kind of liquid fuel space heap |
| CN111627569A (en) * | 2020-05-14 | 2020-09-04 | 中国科学院上海应用物理研究所 | Transuranic fuel and preparation method and transmutation method thereof |
| CN113744907A (en) * | 2020-05-28 | 2021-12-03 | 哈尔滨工程大学 | Molten salt fuel self-sustaining updating module device |
| CN111627572A (en) * | 2020-06-04 | 2020-09-04 | 中国科学院上海应用物理研究所 | Modularized molten salt reactor core and molten salt reactor |
| CN111627572B (en) * | 2020-06-04 | 2022-09-30 | 中国科学院上海应用物理研究所 | Modularized molten salt reactor core and molten salt reactor |
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