CN108198635B - 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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- CN108198635B CN108198635B CN201810146204.4A CN201810146204A CN108198635B CN 108198635 B CN108198635 B CN 108198635B CN 201810146204 A CN201810146204 A CN 201810146204A CN 108198635 B CN108198635 B CN 108198635B
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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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- 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 to be made of fuel fused salt with the moderator lattice cell array made of graphite, the active region includes that neutron 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.Thorium base molten-salt breeder reactor (MSBR) reactor core of the invention passes through the fused salt for changing graphite moderator lattice cell, graphite volume ratio, and reactor core activity is divided into several areas for being mixed with thermography and composing fastly, improves the proliferation performance of heap；By the way that power flattening area is arranged, extend the replacement cycle of graphite to 10 years, so that reactor has negative thermotonus property coefficient；By the way that axial breeding blanket is arranged, the proliferation performance of heap can further improve, while being 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 technique
Molten salt reactor is the reactor that 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, on the other hand also takes into account the function of coolant, when the fuel containing fissioner is molten
Salt with the inlet temperature to be higher than 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 main in the world are as follows: U.S. rubber
The molten-salt breeder reactor (MSBR) MSBR (Molten Salt Breeder Reactor) of Shu Ling National Laboratory, French national science research
Institute without slowing down fused salt fast reactor MSFR (Molten Salt Fueled Reactor), molten salt reactor tests MSRE (Molten Salt
Reactor Experiment), the fused salt transmuting heap MOSART of Japanese FUJI series molten salt reactor and Russia.
It is the use uniquely built up and run that molten salt reactor, which tests MSRE (Molten Salt Reactor Experiment),
Graphite is the molten salt reactor of moderator.Moderator lattice cell is side recessing, the quadrangular that cross section approximation is square.It is adjacent slow
The groove of agent stitches and fastens to form fused salt runner, takes heat out of for fuel salt flowing.The insertion punching of 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 salt 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 has positive temperature anti-
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 makes
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 spectrum by the transformation of thermography Xiang Kuaipu can obtain biggish 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 is with biggish
Fuel hold-up, at high cost, the doubling time of heap is long (being greater than 30 years), and fast reactor technical difficulty is also larger.
Summary of the invention
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 defect that 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 1.08 or more, the graphite replacement cycle up to 10 years, improves 100% or more, temperature is anti-
Property coefficient is answered to be negative.
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 the array that active region includes fuel fused salt and the moderator lattice cell made of graphite, the active region include neutron provide area and
Breeding blanket, it is 2.0:1~2.5:1 that the neutron, which provides area and the volume ratio of the breeding blanket, and the neutron provides the fuel in area
The volume ratio of fused salt and graphite is 1:7.2~1:3.2, the volume ratio of the fuel fused salt of the breeding blanket and graphite be 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 comprehensively 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 arranged
For 1:7.2~1:3.2,1:3.2~1:1.8 is set by the volume ratio of the fuel fused salt of the breeding blanket and graphite.Fuel is molten
The volume ratio of salt and graphite is equal to the area ratio of fuel fused salt and graphite in reactor core cross section.It so can be realized 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
1.08 or more of 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 can all make result generate huge increase, to significantly improve the efficiency of reactor by exponent arithmetic.
Preferably, the active region further includes the first power flattening area, and first power flattening area surrounds the neutron
Offer area, the breeding blanket encirclement first power flattening area, the neutron offer area and first power flattening area
Volume ratio is 1:1~2.0:1, and the fuel fused salt in first power flattening area and the volume ratio of graphite are 1:1.8~1:0.01.
By the way that the first power flattening area is arranged, 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, optimizes thermotonus property coefficient, 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
It is 1:1~2.0:1 with the volume ratio in second power flattening area, the fuel fused salt in first power flattening area and graphite
Volume ratio is 1:1.8~1:0.01, and second power flattening area is fuel fused salt, and the breeding blanket is bordered by and surrounds described the
One power flattening area, first power flattening area, which is bordered by and surrounds the neutron, provides area, and the neutron provides area and is bordered by simultaneously
Around second power flattening area, second power flattening area is located at the center of the active region.Pass through the first power exhibition
The mating reaction in flat area and the second power flattening area, has advanced optimized thermotonus property coefficient, so that thermotonus property coefficient
It is negative, ensure that the safety of reactor, extend 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
It is 1:1~2.0:1 with the volume ratio in second power flattening area, the fuel fused salt in first power flattening area and graphite
Volume ratio is 1:1.8~1:0.01, and second power flattening area is fuel fused salt, and the breeding blanket is bordered by and surrounds described the
One power flattening area, first power flattening area are bordered by and surround second power flattening area, second power flattening
Area, which is bordered by and surrounds the neutron, provides 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, extend the graphite replacement cycle.
Preferably, the fuel fused salt is FLiBe fused salt.
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 two 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 it is in a circular table shape, and the lower reflecting layer is located at the underface of the active region, and in a circular table shape.
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, is used to form the gap between lattice cell for 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 not influencing neutron economy, 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 any combination to get each preferable reality of the present invention
Example.
The positive effect of the present invention is that: thorium base molten-salt breeder reactor (MSBR) reactor core of the invention is by changing graphite moderator
Reactor core activity is divided into several areas for being mixed with thermography and composing fastly by the fused salt of lattice cell, graphite volume ratio, by the breeding ratio of reactor core
It is increased to 1.08 or more；By the way that power flattening area is arranged, extend the replacement cycle of graphite to 10 years so that reactor have it is negative
Thermotonus property coefficient；By the way that axial breeding blanket is arranged, the proliferation performance of heap can further improve, while being conducive to the thermal technology of heap
Hydraulic characteristic(s).
Detailed description of the invention
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 schematic perspective view after the moderator lattice cell combination of the embodiment of the present invention 1.
Fig. 6 is the structural schematic diagram of the template graphite prism of the embodiment of the present invention 1.
Fig. 7 is cross section and the neutron energy relation schematic diagram of the reactor core of the embodiment of the present invention 1.
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 structural schematic diagram of the reactor system of the embodiment of the present invention 1-8.
Description of symbols:
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
The embodiment for further illustrating the present invention below by the mode of embodiment, but therefore not limiting the present invention to
Among range.
Embodiment 1
The high power of the present embodiment mixes power spectrum thorium base molten-salt breeder reactor (MSBR) reactor core, 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 that neutron 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 are 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-
Layer 24 is penetrated, upper reflecting layer 23 is located at right above active region 1, and in a circular table shape, lower reflecting layer 24 is located at immediately below active region 1, is also in
It is round table-like.Graphite materials are saved in reflecting layer 2 under the premise of not influencing neutron economy, and alleviate the positive temperature of graphite reflector
Spend reactivity effect.
Design uses LiF-BeF2-(Th+U)F4Supporting electrolyte of the fused salt as fission fuel and conversion fuel, is made 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 to flow 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 less than 10-6The region of MeV) neutron provide
Area 14 and have 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 flow 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 cools down graphite moderator.Lattice cell is arranged in positive triangle shape.As shown in figure 4, moderator lattice cell is also possible to regular quadrangle
There is fuel duct 3 graphite moderator is flowed through and cooled down for fuel fused salt 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 regular quadrangle.Such as Fig. 5
With shown in Fig. 6, moderator lattice cell is also possible to template graphite prism, has 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 arrange in regular hexagon shape or quadrilateral shape.
As shown in fig. 7, being beneficial to the neutron of proliferation according to U233 fission cross section and the comparison display of Th232 capture cross-section
(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 less than 10-6The region of MeV, i.e. thermal energy range) firmly, so the volume ratio (1:3.2 of the fuel of breeding blanket 11 and graphite
~1:1.8) fuel in neutron offer area 14 and the volume ratio (1:7.2~1:3.2) of graphite are provided, also, in effective use
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, and neutron provides the fuel in area 14 and the volume of graphite
Than for 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 obviously compared with middle section 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 is as Optimal Parameters, by the fuel aperture or lattice cell plate that change moderator lattice cell
The cross circular section diameter of thickness and fin 4, the volume ratio of adjustable fuel and graphite, so that the energy of 1 regional area of active region
It composes different.And the case where 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 for being beneficial to be proliferated and fission, so that the progress neutron of active region 1 be mentioned
The division of donor site 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 suitable neutron provides area 14 and proliferation out
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, the difference is that, as shown in figure 9, the active region of embodiment 2
It joined the first power flattening area 12 in 1.First power flattening area 12 surrounds neutron and provides area 14, and breeding blanket 11 surrounds the first function
The neutron energy spectrum peak value in rate flattened region 12, the first power flattening area 12 is greater 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 setting reactor core center or
It is provided between area 14 and breeding blanket 11 in neutron, neutron energy spectrum is that (energy spectrum peak is located at energy greater than 10 to fast 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, the difference is that, 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 are 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, is increased to 1.1 for breeding ratio, has advanced optimized thermotonus property coefficient, so that temperature-reactive
Coefficient is negative, and 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, the difference is that, 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 are 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 make thermotonus
Property coefficient is negative, and 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 is that, 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 is that, 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 refer in reactor 61 the easy fission quantity of material of generation and the easy fission quantity of material of consumption it
Than, when the ratio is greater 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,
Fission heat in reactor 61 passes through fused salt -63 band of fused salt main heat exchanger to three circuits thermoelectric conversion system (conventional island).This
Outside, it is bypassed by a fused salt, fuel salt is post-processed online, predominantly the neutron poison in removal fission product, mentioned
The breeding ratio of high reactor core.The hot water heated by reactor 61 reaches main pump 62, is transported to main heat exchanger by main pump 62, then reaches
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 fastly, the breeding ratio of reactor core is increased to by salt, graphite volume ratio
More than 1.08；By the way that power flattening area is arranged, extend the replacement cycle of graphite to 10 years, so that reactor has negative temperature anti-
Answer property coefficient；By the way that axial breeding blanket is arranged, the proliferation performance of heap 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
Active region includes the array of fuel fused salt and the moderator lattice cell made of graphite, and the active region includes that neutron provides Qu Hezeng
Area is grown, it is 2.0:1~2.5:1 that the neutron, which provides area and the volume ratio of the breeding blanket, and the fuel that the neutron provides area is molten
The volume ratio of salt and graphite is 1:7.2~1:3.2, and 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, first power flattening area surround the neutron and provide area, and the breeding blanket surrounds first power flattening area,
It is 1:1~2.0:1, the combustion in first power flattening area that the neutron, which provides area and the volume ratio in 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 1:1~2.0 that the neutron, which provides area and the volume ratio in second power flattening area:
1, the fuel fused salt in 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 first power flattening area, and first power flattening area is bordered by simultaneously
Area is provided around the neutron, the neutron provides area and is bordered by and surrounds 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 1:1~2.0 that the neutron, which provides area and the volume ratio in second power flattening area:
1, the fuel fused salt in 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 first power flattening area, and first power flattening area is bordered by simultaneously
Around second power flattening area, second power flattening area, which is bordered by and surrounds the neutron, provides area, and the neutron mentions
Donor site is located at the center of the active region.
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 salt.
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 two 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 in a circular table shape, and the lower reflecting layer is located at
The underface of the active region, and it is in a circular table shape.
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
It is equipped with fuel duct, 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 of 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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| CN109192251A (en) * | 2018-08-09 | 2019-01-11 | 华南理工大学 | A kind of calculation method of the three-dimensional fine power distribution of solid fuel molten salt reactor |
| CN109273121B (en) * | 2018-12-07 | 2020-11-27 | 中国科学院上海应用物理研究所 | Molten salt fuel multi-reactor system |
| CN110310750B (en) * | 2019-07-08 | 2021-05-14 | 华南理工大学 | Molten salt stack capable of simultaneously producing tritium and C14 |
| CN110444311B (en) * | 2019-08-13 | 2021-05-18 | 中国科学院上海应用物理研究所 | Method for transmuting transuranic elements by liquid 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 |
| 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 |
| CN112863725B (en) * | 2021-01-21 | 2022-12-09 | 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 |
| 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 |
| 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 |
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| CN101299351B (en) * | 2008-06-27 | 2011-09-07 | 张育曼 | Stack core of water-cooling double-section breeding nuclear reactor as well as nuclear reactor using the same |
| CN102623078A (en) * | 2012-03-30 | 2012-08-01 | 中国科学院合肥物质科学研究院 | Efficient nuclear waste evolution sub-critical reactor core based on mixed energy spectrum |
| CN103093836B (en) * | 2013-01-15 | 2014-05-14 | 西安交通大学 | Fusion driving subcritical cladding of transmutation subordinate actinium series nuclide |
| CN103886921B (en) * | 2014-03-13 | 2016-06-29 | 清华大学 | A kind of full molten salt fuel hybrid reactor system of Th-U self-sustaining cycle and operation method thereof |
| CN104409109A (en) * | 2014-09-26 | 2015-03-11 | 吕应中 | Ultrahigh specific power thermal neutron thorium breeder reactor apparatus and method for nuclear fuel propagation |
| US10008293B2 (en) * | 2015-09-18 | 2018-06-26 | Utah Green Energy Technologies, Llc | Molten salt reactor |
| WO2017070791A1 (en) * | 2015-10-30 | 2017-05-04 | Terrestrial Energy Inc. | Molten salt nuclear reactor |
| CN105405476B (en) * | 2015-10-30 | 2016-11-23 | 西安交通大学 | A kind of fast neutron reactor being capable of propagation and burning power and energy |
| KR101717942B1 (en) * | 2016-02-03 | 2017-04-04 | 세종대학교산학협력단 | Small modular nuclear reactor core and nuclear reactor having the same |
| CN105976879B (en) * | 2016-05-09 | 2019-05-07 | 中国科学院上海应用物理研究所 | A kind of assembly type molten salt reactor |
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