CN108198635A - A kind of thorium base molten-salt breeder reactor (MSBR) reactor core - Google Patents
A kind of thorium base molten-salt breeder reactor (MSBR) reactor core Download PDFInfo
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- CN108198635A CN108198635A CN201810146204.4A CN201810146204A CN108198635A CN 108198635 A CN108198635 A CN 108198635A CN 201810146204 A CN201810146204 A CN 201810146204A CN 108198635 A CN108198635 A CN 108198635A
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
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- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/22—Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel
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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 invention discloses a kind of thorium base molten-salt breeder reactor (MSBR) reactor cores, including active region and reflecting layer, active region described in the reflecting layer covers, the active region is that moderator lattice cell array is formed by fuel fused salt and made of graphite, the active region includes neutron and provides area, power flattening area and breeding blanket, the power flattening area surrounds the neutron and provides area, and the breeding blanket surrounds the power flattening area.Reactor core activity is divided into several areas for being mixed with thermography and composing soon, improves the proliferation performance of heap by the thorium base molten-salt breeder reactor (MSBR) reactor core of the present invention by changing fused salt, the graphite volume ratio of graphite moderator lattice cell；By setting power flattening area, extend the replacement cycle of graphite to 10 years so that reactor has negative thermotonus property coefficient；By setting axial breeding blanket, the proliferation performance of heap is can further improve, while be conducive to the hot-working hydraulic characteristic of heap.
Description
Technical field
The present invention relates to molten salt reactor Core Design fields, and in particular to a kind of thorium base molten-salt breeder reactor (MSBR) reactor core.
Background technology
Molten salt reactor is that the reactor of liquid fuel is uniquely used in six kinds of forth generation reactor candidate's heap-type, inherently safe
Property, economy, prevention of nuclear proliferation and nuclear fuel sustainable development etc. there is its unique advantage.The fuel one side nothing of molten salt reactor
It needs to be manufactured as traditional reactor, the function of cooling agent is on the other hand also taken into account, when the fuel containing fissioner melts
Salt with be higher than the inlet temperature of itself fusing point enter reactor core and it is critical when, fuel occurs fission and generates heat, while again will be hot
Band is measured to secondary circuit.
Since molten salt reactor concept is born, main molten-salt breeder reactor (MSBR) Conceptual Design Study is mainly in the world：U.S. rubber
The molten-salt breeder reactor (MSBR) MSBR (Molten Salt Breeder Reactor) of Shu Ling National Laboratories, French national science research
Institute without slowing down fused salt fast reactor MSFR (Molten Salt Fueled Reactor), molten salt reactor experiment MSRE (Molten Salt
Reactor Experiment), the fused salt transmuting heap MOSART of Japanese FUJI series molten salt reactor and Russia.
Molten salt reactor experiment MSRE (Molten Salt Reactor Experiment) is the use uniquely built up and run
Graphite is the molten salt reactor of moderator.Moderator lattice cell is side recessing, and cross section is approximately the quadrangular of square.It is adjacent slow
The groove of agent is stitched together to form fused salt runner, and heat is taken out of for fuel salt flowing.Punching is inserted into moderator lattice cell lower end
Turbogrid plates in fix its position, be arranged into approximate circle reactor core.
The typical heap-type of thermal reactor is MSBR, using FLiBe fused salts as supporting electrolyte, graphite as moderator and reflecting layer,
About 560 DEG C of reactor core inlet temperature, about 700 DEG C of outlet temperature, thermal power 2250MW.According to assessment, MSBR is anti-with positive temperature
Property coefficient is answered, the safety of reactor is seriously affected, and its heap core graphite need to be replaced with 4 years for the period, this causes
The cost of reactor is also higher, and breeding ratio is 1.06 or so.
The Typical Representative MSFR of fast reactor is that the molten salt reactor without graphite that French national science research institute CNRS is proposed is fast
Heap concept.MSFR power spectrums from thermography to the transformation composed soon can obtain larger negative temperature reactivity coefficient and cavitation efficiency, compared with
Big breeding ratio and without particular advantages such as graphite service life limitations.But the slowing properties of villiaumite is preferable so that MSFR has larger
Fuel hold-up, of high cost, the doubling time length (being more than 30 years) of heap, and fast reactor technical difficulty is also larger.
Invention content
The technical problem to be solved by the present invention is in order to overcome in the prior art reactor core breeding ratio be no more than 1.06, graphite is more
The period is changed no more than 4 years, the defects of thermotonus property coefficient is positive, provides a kind of high power mixing power spectrum thorium base molten-salt breeder reactor (MSBR)
Reactor core, for the breeding ratio of reactor core up to more than 1.08, the graphite replacement cycle up to 10 years, improves more than 100%, temperature is anti-
It is negative to answer property coefficient.
The present invention is to solve above-mentioned technical problem by following technical proposals：
A kind of thorium base molten-salt breeder reactor (MSBR) reactor core, including active region and reflecting layer, active region described in the reflecting layer covers, institute
State active region include fuel fused salt and made of graphite moderator lattice cell array, the active region include neutron provide area and
Breeding blanket, it is 2.0 that the neutron, which provides area and the volume ratio of the breeding blanket,:1~2.5:1, the neutron provides the fuel in area
The volume ratio of fused salt and graphite is 1:7.2~1:3.2, the fuel fused salt of the breeding blanket and the volume ratio of graphite are 1:3.2~
1:1.8.It is calculated by a large amount of different fuel fused salt and the reactor core of graphite volume ratio, and considers effective multiplication factor, temperature
Degree reactivity coefficient and breeding ratio are in optimized selection, and the volume ratio of fuel fused salt and graphite that the neutron provides area is set
It is 1:7.2~1:3.2, the volume ratio of the fuel fused salt of the breeding blanket and graphite is set as 1:3.2~1:1.8.Fuel melts
The volume ratio of salt and graphite is equal to the area of the fuel fused salt and graphite ratio in reactor core cross section.It can so realize comprehensive thermography
The advantages of reactor and fast spectrum reactor, reach higher breeding ratio so that breeding ratio is increased to this from the 1.06 of the prior art
More than 1.08 invention.Since in fuel fission, fissionable nucleus subnumber is exponentially increased by the truth of a matter of breeding ratio, therefore i.e.
Just the raising of very little by exponent arithmetic, can all make result generate huge increase, so as to significantly improve the efficiency of reactor.
Preferably, the active region further includes the first power flattening area, and the first power flattening area surrounds the neutron
Offer area, breeding blanket encirclement the first power flattening area, the neutron offer area and the first power flattening area
Volume ratio is 1:1~2.0:1, the fuel fused salt in the first power flattening area and the volume ratio of graphite are 1:1.8~1:0.01.
By setting the first power flattening area, core power distribution is flattened, by by the fuel fused salt and stone in the first power flattening area
The volume ratio of ink is set as 1:1.8~1:0.01, thermotonus property coefficient is optimized, extends the graphite replacement cycle.
Preferably, the active region further includes the first power flattening area and the second power flattening area, and the neutron provides area
Volume ratio with the second power flattening area is 1:1~2.0:1, the fuel fused salt in the first power flattening area and graphite
Volume ratio is 1:1.8~1:0.01, the second power flattening area is fuel fused salt, and the breeding blanket is bordered by and surrounds described the
One power flattening area, the first power flattening area are bordered by and surround the neutron offer area, and the neutron provides area and is bordered by simultaneously
Around the second power flattening area, the second power flattening area is located at the center of the active region.Pass through the first power exhibition
Flat area and the mating reaction in the second power flattening area, have advanced optimized thermotonus property coefficient so that thermotonus property coefficient
It is negative, ensure that the safety of reactor, extends the graphite replacement cycle.
Preferably, the active region further includes the first power flattening area and the second power flattening area, and the neutron provides area
Volume ratio with the second power flattening area is 1:1~2.0:1, the fuel fused salt in the first power flattening area and graphite
Volume ratio is 1:1.8~1:0.01, the second power flattening area is fuel fused salt, and the breeding blanket is bordered by and surrounds described the
One power flattening area, the first power flattening area are bordered by and surround the second power flattening area, second power flattening
Area is bordered by and surrounds the neutron offer area, and the neutron provides the center that area is located at the active region.By by the first power
Flattened region and the second power flattening area are stacked, and have advanced optimized thermotonus property coefficient so that thermotonus property coefficient
It is negative, ensure that the safety of reactor, extends the graphite replacement cycle.
Preferably, the fuel fused salt is FLiBe fused salts.
Preferably, the fuel fused salt is LiF-BeF2-(Th+U)F4Fused salt.
Preferably, the fuel fused salt is villaumite.
Preferably, the breeding blanket includes radial breeder and axial breeding blanket, the radial breeder and the axial direction
Breeding blanket provides the neutron in area is wrapped in.Such structure is capable of providing neutron economy.
Preferably, the reflecting layer includes radial reflector and axial reflecting layer, and the radial reflector is centered around activity
Area periphery, the axial direction reflecting layer are located at the both sides of the radial reflector.
Preferably, the axial reflecting layer includes upper reflecting layer and lower reflecting layer, and the upper reflecting layer is located at the activity
The surface in area, and be in round table-like, the lower reflecting layer is located at the underface of the active region, and in round table-like.
Preferably, the centre of the moderator lattice cell is provided with fuel duct, for flowing through fuel fused salt and cooling down stone
Black moderator.By changing the diameter in fuel duct, the volume ratio of fuel fused salt and graphite can be changed.
Preferably, the side of the moderator lattice cell is provided with fin, and the gap being used to form between lattice cell supplies fuel fused salt
It circulates and cools down graphite moderator.By changing the size of fin, the size in the gap between lattice cell can be changed, and then can change
Become the volume ratio of fuel fused salt and graphite.
Graphite materials are saved under the premise of neutron economy is not influenced, and alleviate the positive thermotonus of graphite reflector
Property effect.
On the basis of common knowledge of the art, above-mentioned each optimum condition can be combined arbitrarily to get each preferable reality of the present invention
Example.
The positive effect of the present invention is：The thorium base molten-salt breeder reactor (MSBR) reactor core of the present invention is by changing graphite moderator
Reactor core activity is divided into several areas for being mixed with thermography and composing soon by the fused salt of lattice cell, graphite volume ratio, by the breeding ratio of reactor core
It is increased to more than 1.08；By setting power flattening area, extend the replacement cycle of graphite to 10 years so that reactor has negative
Thermotonus property coefficient；By setting axial breeding blanket, the proliferation performance of heap is can further improve, while be conducive to the thermal technology of heap
Hydraulic characteristic(s).
Description of the drawings
Fig. 1 is the cross section structure schematic diagram of the reactor core of the embodiment of the present invention 1.
Fig. 2 is the side structure schematic view of the reactor core of the embodiment of the present invention 1.
Fig. 3 is a kind of cross section structure schematic diagram of moderator lattice cell of the embodiment of the present invention 1.
Fig. 4 is the cross section structure schematic diagram of another moderator lattice cell of the embodiment of the present invention 1.
Fig. 5 is the dimensional structure diagram after the moderator lattice cell combination of the embodiment of the present invention 1.
Fig. 6 is the structure diagram of the template graphite prism of the embodiment of the present invention 1.
Fig. 7 is the cross section of the reactor core of the embodiment of the present invention 1 and neutron energy relation schematic diagram.
Fig. 8 is the side structure schematic view of the moderator lattice cell of the embodiment of the present invention 1.
Fig. 9 is the cross section structure schematic diagram of the reactor core of the embodiment of the present invention 2.
Figure 10 is the cross section structure schematic diagram of the reactor core of the embodiment of the present invention 3.
Figure 11 is the cross section structure schematic diagram of the reactor core of the embodiment of the present invention 4.
Figure 12 is the structure diagram of the reactor system of the embodiment of the present invention 1-8.
Reference sign：
Active region 1
Breeding blanket 11
First power flattening area 12
Second power flattening area 13
Neutron provides area 14
Reflecting layer 2
Radial reflector 21
Axial reflecting layer 22
Upper reflecting layer 23
Lower reflecting layer 24
Fuel duct 3
Fin 4
Moderator lattice cell head 51
Moderator lattice cell end 52
Reactor 61
Main pump 62
Main heat exchanger 63
After-treatment system 64
Specific embodiment
It is further illustrated the present invention below by the mode of embodiment, but the embodiment therefore not limited the present invention to
Among range.
Embodiment 1
The high power mixing power spectrum thorium base molten-salt breeder reactor (MSBR) reactor core of the present embodiment, as shown in Figure 1, including active region 1 and instead
Layer 2 is penetrated, reflecting layer 2 coats active region 1, and active region 1 includes neutron and provides area 14 and breeding blanket 11, and neutron provides the neutron in area 14
Energy spectrum peak is less than 10-6MeV, the neutron energy spectrum peak value of breeding blanket 11 is 10-6MeV~10-3MeV。
As shown in Fig. 2, reflecting layer 2 is in 1 periphery of active region and upper/lower terminal.Reflecting layer 2 can also be divided into radial reflector 21
With axial reflecting layer 22.Radial reflector 21 is centered around 1 periphery of active region.Axial reflecting layer 22 is divided for upper reflecting layer 23 and lower anti-
Penetrate layer 24, upper reflecting layer 23 is located at right over active region 1, and in round table-like, lower reflecting layer 24 is located at 1 underface of active region, is also in
It is round table-like.Graphite materials are saved in reflecting layer 2 under the premise of neutron economy is not influenced, and alleviate the positive temperature of graphite reflector
Spend reactivity effect.
Design is using LiF-BeF2-(Th+U)F4Fused salt is made as fission fuel and the supporting electrolyte of conversion fuel using graphite
For moderator and reflecting layer.Reactor core includes active region 1 and reflecting layer 2, and active region 1 is by graphite moderator lattice cell and flows through wherein
Fuel fused salt composition, the design of graphite moderator lattice cell can by change several crucial geometric dimensions come flexible modulation fused salt,
Graphite volume ratio, by reactor core be divided into thermal-neutron spectrum (can spectrum peak be located at energy be less than 10-6The region of MeV) neutron provide
Area 14 and with epithermal neutron spectrum (can spectrum peak be located at 10-6MeV~10-3MeV can area) breeding blanket 11.
As shown in figure 3, moderator lattice cell can be graphite hexagonal prisms, there is fuel duct 3 to be flowed through for fuel fused salt for centre
And graphite moderator is cooled down, there is fin 4 on non-conterminous three sides, to form the gap between lattice cell for fuel fused salt stream
Lead to and cool down graphite moderator.Lattice cell is arranged in positive triangle shape.As shown in figure 4, moderator lattice cell can also be square
There is fuel duct 3 to flow through for fuel fused salt and cool down graphite moderator for graphite prism, centre, and four sides are fin 4, to
The gap formed between lattice cell circulates for fuel fused salt and cools down graphite moderator, and wherein lattice cell is arranged in square.Such as Fig. 5
Shown in Fig. 6, moderator lattice cell can also be template graphite prism, have fin 4 on plate, to form the gap between lattice cell for combustion
Material fused salt circulates and cools down graphite moderator.Lattice cell can be in that regular hexagon shape or quadrilateral shape are arranged.
As shown in fig. 7, according to U233 fission cross sections and the comparison display of Th232 capture cross-sections, it is beneficial to the neutron of proliferation
(energy spectrum peak is located at 10 to power spectrum-5MeV~10-3MeV energy area, i.e. resonance region) to be relatively beneficial to neutron energy spectrum (the energy spectral peak of fission
Value is located at energy and is less than 10-6The region of MeV, i.e. thermal energy range) firmly, so the volume ratio (1 of the fuel of breeding blanket 11 and graphite:3.2
~1:1.8) fuel in area 14 and the volume ratio (1 of graphite are provided more than neutron:7.2~1:3.2), also, in efficiently using
Son provides the neutron that area 14 generates, and provides neutron to area 14 and is placed in inside active region 1, and breeding blanket 11 is placed in 1 periphery of active region.
In the present embodiment, the fuel of breeding blanket 11 and the volume ratio of graphite are 1:2.8, neutron provides the fuel in area 14 and the volume of graphite
Than being 1:6.
Breeding blanket 11 can also be further divided into radial breeder (not shown) and axial breeding blanket (not shown),
Neutron is provided in area 14 is wrapped in, to provide neutron economy.Radial breeder has the teasehole of graphite hexagonal prisms lattice cell
Diameter and side fin 4.Axial breeding blanket is formed by the axial geometry of graphite moderator lattice cell, as shown in figure 8, graphite
Agent lattice cell includes moderator lattice cell head 51 and moderator lattice cell end 52, and lattice cell both ends caput cross section is significantly compared with stage casing cross section
Small, fuel graphite volume ratio is big, is beneficial to be proliferated.
Reactor modeling, and the selected wherein fuel aperture of flexibly changing or lattice cell plate are carried out using card software MCNP is covered
The cross circular section diameter of thickness and fin 4 parameter as an optimization, by changing the fuel aperture of moderator lattice cell or lattice cell plate
The cross circular section diameter of thickness and fin 4 can adjust the volume ratio of fuel and graphite so that the energy of 1 regional area of active region
It composes different.And situation about being changed according to the neutron-capture cross section of Th and the fission cross section of U with neutron energy, preferably go out to close
Suitable fuel and graphite volume ratio to respectively obtain the power spectrum that is beneficial to be proliferated and fission, carry so as to which active region 1 is carried out neutron
For the division of area 14 and breeding blanket 11.Neutron provides area 14 and breeding blanket 11 is substantially arranged in circle.According to what is be calculated
Effective multiplication factor, breeding ratio and thermotonus property coefficient optimize, and preferably go out suitable neutron and provide area 14 and proliferation
The equivalent diameter in area 11.The core thermal power that the present embodiment provides is 2250MW.
In the present embodiment, the breeding ratio for simulating the reactor core being calculated is increased to 1.085.
Embodiment 2
The structure of embodiment 2 is substantially the same manner as Example 1, and the difference lies in as shown in figure 9, the active region of embodiment 2
The first power flattening area 12 is added in 1.First power flattening area 12 surrounds neutron and provides area 14, and breeding blanket 11 surrounds the first work(
Rate flattened region 12, the neutron energy spectrum peak value in the first power flattening area 12 are more than 10-3MeV has fast neutron spectrum.First power flattening
Area 12 can flatten core power distribution and optimization thermotonus property coefficient, the first power flattening area 12 be arranged on reactor core center or
It is provided between area 14 and breeding blanket 11 in neutron, for fast spectrum, (energy spectrum peak is located at energy more than 10 to neutron energy spectrum-3The region of MeV,
Fuel graphite volume ratio 1:1.8~1:0.01).Control rod is placed in power flattening area.
In the present embodiment, according to Computer simulation results, breeding ratio has been increased to 1.09, and the replacement cycle of graphite extends
By 10 years so that reactor has negative thermotonus property coefficient.
Embodiment 3
The structure of embodiment 3 is substantially the same manner as Example 2, and the difference lies in as shown in Figure 10, active region 1 further includes
First power flattening area 12 and the second power flattening area 13, the fuel fused salt in the first power flattening area 12 and the volume ratio of graphite are
1:1, the second power flattening area 13 is fuel fused salt, and breeding blanket 11 is bordered by and around the first power flattening area 12, the first power exhibition
Flat area 12 is bordered by and provides area 14 around neutron, and neutron provides area 14 and is bordered by and around the second power flattening area 13, the second power
Flattened region 13 is located at the center of active region 1.According to Computer simulation results, pass through the first power flattening area 12 and the second power exhibition
The mating reaction in flat area 13,1.1 are increased to by breeding ratio, have advanced optimized thermotonus property coefficient so that temperature-reactive
Coefficient is negative, ensure that the safety of reactor, extends the graphite replacement cycle.
Embodiment 4
The structure of embodiment 4 is substantially the same manner as Example 2, and the difference lies in as shown in figure 11, active region 1 further includes
First power flattening area 12 and the second power flattening area 13, the fuel fused salt in the first power flattening area 12 and the volume ratio of graphite are
1:1, the second power flattening area 13 is fuel fused salt, and breeding blanket 11 is bordered by and around the first power flattening area 12, the first power exhibition
Flat area 12 is bordered by and around the second power flattening area 13, and the second power flattening area 13 is bordered by and provides area 14, neutron around neutron
The center that area 14 is located at active region 1 is provided.According to Computer simulation results, by by the first power flattening area 12 and the second power
Flattened region 13 is stacked, and breeding ratio is increased to 1.1, has advanced optimized thermotonus property coefficient, and cause thermotonus
Property coefficient is negative, ensure that the safety of reactor, extends the graphite replacement cycle.
Embodiment 5-8
Embodiment 5-8 is substantially the same manner as Example 1, the difference lies in, the fuel of breeding blanket 11 and the volume ratio of graphite,
And neutron provide area 14 fuel and graphite volume ratio it is different.
The Computer simulation results of embodiment 5-8 are as shown in table 1：
Table 1：The Computer simulation results of embodiment 5-8
Comparative example 1-4
Comparative example 1-4 is substantially the same manner as Example 1, the difference lies in, the fuel of breeding blanket 11 and the volume ratio of graphite,
And neutron provide area 14 fuel and graphite volume ratio it is different.The Computer simulation results of comparative example 1-4 such as table 2
Shown in：
Table 2：The Computer simulation results of comparative example 1-4
In table 2, conversion than the easy fission quantity of material that refers to generate reactor 61 in and consumption easily fission quantity of material it
Than, when the ratio is more than 1, referred to as breeding ratio.Between the generation rate and disappearance rate of the not critical neutron for referring to reactor no longer
Balance prevents chain reaction from the state that is continued for down.
As shown in figure 12, high power of the invention mixing power spectrum thorium base molten-salt breeder reactor (MSBR) reactor core is set in reactor 61,
The thermoelectric conversion system (conventional island) that fission heat in reactor 61 passes through fused salt -63 band of fused salt main heat exchanger to three circuits.This
Outside, it is bypassed by a fused salt, fuel salt is post-processed online, predominantly removed the neutron poison in fission product, carry
The breeding ratio of high reactor core.Main pump 62 is reached by the hot water that reactor 61 heats, main heat exchanger is transported to by main pump 62, is then reached
After-treatment system 64.
The high power mixing power spectrum thorium base molten-salt breeder reactor (MSBR) reactor core of the present embodiment is by changing the molten of graphite moderator lattice cell
Reactor core activity is divided into several areas for being mixed with thermography and composing soon, the breeding ratio of reactor core is increased to by salt, graphite volume ratio
More than 1.08；By setting power flattening area, extend the replacement cycle of graphite to 10 years so that reactor is anti-with negative temperature
Answer property coefficient；By setting axial breeding blanket, the proliferation performance of heap is can further improve, while the thermal-hydraulic for being conducive to heap is special
Property.
Although specific embodiments of the present invention have been described above, it will be appreciated by those of skill in the art that this is only
For example, protection scope of the present invention is to be defined by the appended claims.Those skilled in the art without departing substantially from
Under the premise of the principle and substance of the present invention, many changes and modifications may be made, but these change and
Modification each falls within protection scope of the present invention.
Claims (12)
1. a kind of thorium base molten-salt breeder reactor (MSBR) reactor core, including active region and reflecting layer, active region described in the reflecting layer covers is described
The array of active region moderator lattice cell including fuel fused salt and made of graphite, the active region include neutron and provide Qu Hezeng
Area is grown, it is 2.0 that the neutron, which provides area and the volume ratio of the breeding blanket,:1~2.5:1, the fuel that the neutron provides area melts
The volume ratio of salt and graphite is 1:7.2~1:3.2, the fuel fused salt of the breeding blanket and the volume ratio of graphite are 1:3.2~1:
1.8。
2. thorium base molten-salt breeder reactor (MSBR) reactor core as described in claim 1, which is characterized in that the active region further includes the first power
Flattened region, the first power flattening area surround the neutron and provide area, and the breeding blanket surrounds the first power flattening area,
It is 1 that the neutron, which provides area and the volume ratio in the first power flattening area,:1~2.0:1, the combustion in the first power flattening area
The volume ratio for expecting fused salt and graphite is 1:1.8~1:0.01.
3. thorium base molten-salt breeder reactor (MSBR) reactor core as claimed in claim 2, which is characterized in that the active region further includes the first power
Flattened region and the second power flattening area, it is 1 that the neutron, which provides area and the volume ratio in the second power flattening area,:1~2.0:
1, the fuel fused salt in the first power flattening area and the volume ratio of graphite are 1:1.8~1:0.01, second power flattening
Area is fuel fused salt, and the breeding blanket is bordered by and surrounds the first power flattening area, and the first power flattening area is bordered by simultaneously
Area is provided around the neutron, the neutron provides area and is bordered by and surrounds the second power flattening area, the second power exhibition
Flat area is located at the center of the active region.
4. thorium base molten-salt breeder reactor (MSBR) reactor core as claimed in claim 2, which is characterized in that the active region further includes the first power
Flattened region and the second power flattening area, it is 1 that the neutron, which provides area and the volume ratio in the second power flattening area,:1~2.0:
1, the fuel fused salt in the first power flattening area and the volume ratio of graphite are 1:1.8~1:0.01, second power flattening
Area is fuel fused salt, and the breeding blanket is bordered by and surrounds the first power flattening area, and the first power flattening area is bordered by simultaneously
Around the second power flattening area, the second power flattening area is bordered by and surrounds the neutron offer area, and the neutron carries
It is located at the center of the active region for area.
5. thorium base molten-salt breeder reactor (MSBR) reactor core as described in claim 1, which is characterized in that the fuel fused salt is FLiBe fused salts.
6. thorium base molten-salt breeder reactor (MSBR) reactor core as described in claim 1, which is characterized in that the fuel fused salt is LiF-BeF2-
(Th+U)F4Fused salt.
7. thorium base molten-salt breeder reactor (MSBR) reactor core as described in claim 1, which is characterized in that the fuel fused salt is villaumite.
8. thorium base molten-salt breeder reactor (MSBR) reactor core as described in claim 1, which is characterized in that the breeding blanket includes radial breeder
With axial breeding blanket, the radial breeder and the axial breeding blanket provide the neutron in area is wrapped in.
9. thorium base molten-salt breeder reactor (MSBR) reactor core as described in claim 1, which is characterized in that the reflecting layer includes radial reflector
With axial reflecting layer, the radial reflector is centered around the periphery of the active region, and the axial direction reflecting layer is located at the radial direction
The both sides in reflecting layer.
10. thorium base molten-salt breeder reactor (MSBR) reactor core as claimed in claim 9, which is characterized in that the axial direction reflecting layer includes upper anti-
Layer and lower reflecting layer are penetrated, the upper reflecting layer is located at the surface of the active region, and is in round table-like, and the lower reflecting layer is located at
The underface of the active region, and in round table-like.
11. thorium base molten-salt breeder reactor (MSBR) reactor core as described in claim 1, which is characterized in that the centre of the moderator lattice cell is set
Fuel duct is equipped with, for flowing through fuel fused salt and cooling down graphite moderator.
12. the thorium base molten-salt breeder reactor (MSBR) reactor core as described in any one in claim 1 to 11, which is characterized in that the slowing down
The side of agent lattice cell is provided with fin, is used to form the gap between lattice cell, circulates for fuel fused salt and cools down graphite moderator.
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Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN112863725A (en) * | 2021-01-21 | 2021-05-28 | 中国科学院上海应用物理研究所 | Method and system for producing Mo-99 by liquid molten salt reactor |
| CN113270206A (en) * | 2021-03-29 | 2021-08-17 | 中国核电工程有限公司 | Small-sized prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels |
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| CN109273121A (en) * | 2018-12-07 | 2019-01-25 | 中国科学院上海应用物理研究所 | A kind of more shut-down systems of molten salt fuel |
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| CN110310750A (en) * | 2019-07-08 | 2019-10-08 | 华南理工大学 | It is a kind of to produce tritium and the molten salt reactor of C14 simultaneously |
| CN110444311A (en) * | 2019-08-13 | 2019-11-12 | 中国科学院上海应用物理研究所 | The method of liquid molten salt reactor transmuting transuranic element |
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| 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 |
| CN112259263A (en) * | 2020-10-26 | 2021-01-22 | 中国科学院上海应用物理研究所 | Three-channel molten salt reactor core structure and three-channel molten salt reactor system |
| CN112259263B (en) * | 2020-10-26 | 2022-08-02 | 中国科学院上海应用物理研究所 | Three-channel molten salt reactor core structure and three-channel molten salt reactor system |
| CN112863725A (en) * | 2021-01-21 | 2021-05-28 | 中国科学院上海应用物理研究所 | Method and system for producing Mo-99 by liquid molten salt reactor |
| CN113270206A (en) * | 2021-03-29 | 2021-08-17 | 中国核电工程有限公司 | Small-sized prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels |
| CN113270206B (en) * | 2021-03-29 | 2023-12-22 | 中国核电工程有限公司 | Small prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels |
| CN114496314A (en) * | 2022-02-17 | 2022-05-13 | 中国核动力研究设计院 | Fast neutron thermal neutron concentric circle type partitioned ultrahigh flux reactor core |
| CN114496314B (en) * | 2022-02-17 | 2024-02-13 | 中国核动力研究设计院 | Ultra-high flux reactor core with fast neutron thermal neutron concentric circle type partition |
| US12012827B1 (en) | 2023-09-11 | 2024-06-18 | Natura Resources LLC | Nuclear reactor integrated oil and gas production systems and methods of operation |
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