CN107093467B - The method of mox fuel component and flattening power for transmuting and flattening power - Google Patents
The method of mox fuel component and flattening power for transmuting and flattening power Download PDFInfo
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- CN107093467B CN107093467B CN201710193424.8A CN201710193424A CN107093467B CN 107093467 B CN107093467 B CN 107093467B CN 201710193424 A CN201710193424 A CN 201710193424A CN 107093467 B CN107093467 B CN 107093467B
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- 239000000446 fuel Substances 0.000 title claims abstract description 240
- 238000000034 method Methods 0.000 title claims abstract description 13
- 150000001257 actinium Chemical class 0.000 claims abstract description 54
- QQINRWTZWGJFDB-UHFFFAOYSA-N actinium atom Chemical group [Ac] QQINRWTZWGJFDB-UHFFFAOYSA-N 0.000 claims abstract description 4
- 238000003491 array Methods 0.000 claims description 12
- 238000002485 combustion reaction Methods 0.000 claims description 6
- 229910052767 actinium Inorganic materials 0.000 claims description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 31
- 230000004992 fission Effects 0.000 abstract description 18
- 238000006243 chemical reaction Methods 0.000 abstract description 17
- 230000000694 effects Effects 0.000 abstract description 12
- 230000002708 enhancing effect Effects 0.000 abstract description 5
- 230000008569 process Effects 0.000 abstract description 4
- 238000010586 diagram Methods 0.000 description 6
- 238000012545 processing Methods 0.000 description 6
- 229910052778 Plutonium Inorganic materials 0.000 description 5
- 238000001816 cooling Methods 0.000 description 5
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 238000007599 discharging Methods 0.000 description 4
- 238000010348 incorporation Methods 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 238000004364 calculation method Methods 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 2
- 208000019155 Radiation injury Diseases 0.000 description 1
- 241000030614 Urania Species 0.000 description 1
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 230000005284 excitation Effects 0.000 description 1
- 239000011521 glass Substances 0.000 description 1
- 229910001385 heavy metal Inorganic materials 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- FLDALJIYKQCYHH-UHFFFAOYSA-N plutonium(IV) oxide Inorganic materials [O-2].[O-2].[Pu+4] FLDALJIYKQCYHH-UHFFFAOYSA-N 0.000 description 1
- 238000012805 post-processing Methods 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
- G21C3/328—Relative disposition of the elements in the bundle lattice
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/48—Non-aqueous processes
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The method that the present invention relates to a kind of for transmuting and flattens the mox fuel component of power and flattens power.It is a kind of for transmuting and flattening power mox fuel component, including doping fuel rod, fuel rod and guide pipe, the doping fuel rod be the fuel rod for adulterating long-life secondary actinium series nucleic；The doping fuel rod, the fuel rod and the guide pipe forming array, each doping fuel rod are adjacent with a guide pipe.The fuel rod adjacent with guide pipe is set doping fuel rod by mox fuel component of the present invention for transmuting and flattening power, adulterates the long-life time actinium series nucleic in fuel rod in neutron field by transmuting, to reduce the cost and difficulty of spentnuclear fuel final process.Meanwhile the fission reaction rate for adulterating fuel rod is weakened, to reduce in mox fuel component around guide pipe higher power originally, to achieve the effect that the power, the enhancing reactor core safety that flatten mox fuel component.
Description
Technical field
The present invention relates to nuclear engineering technical fields, have transmuting time actinium series nucleic and flattening power function more particularly to one kind
The mox fuel component of energy.
Background technique
With the rapid growth of China's economy, the demand to the energy is greatly increased, especially after signing Paris agreement,
Develop green energy resource and has become the most important thing.Nuclear energy have the characteristics that efficiently, cleaning and it is stable, meet China the energy need
It asks.In recent years, China's pressurized-water reactor nuclear power plant rapid growth, but the spentnuclear fuel accumulation therefore generated also quicklys increase.These are weary
Fuel lifetime is long, radiotoxicity is big, the long-term living environment for threatening the mankind.
Spentnuclear fuel handles half-life period longer secondary actinium series nucleic in problem, especially spentnuclear fuel237Np、241Am、243Am、244Cm and245The processing problem of Cm is long-standing problem people and there is the problem largely disputed on.In face of the situation of this sternness,
How to deal carefully with, dispose spentnuclear fuel, is one to ensure the Environmental security of descendants and the sustainable development of China's nuclear energy
The significant problem that must be solved.Currently, to the processing of spentnuclear fuel, there are mainly two types of schemes in the world.One is using the U.S. as representative
Open circulation scheme, another kind is the closed cycle scheme using European Union as representative.Open circulation scheme fills, and is by weary combustion
Material is directly buried in underground through in a few years cooling and then with glass or concrete package.But containing higher in spentnuclear fuel
Fissionable isotope, directly landfill is unable to fully using these fissible resources；In addition, due to gradation actinium series in the middle part of spentnuclear fuel
The half-life period of element is very long, and whether the container for wrapping up spentnuclear fuel is able to bear the sufficiently long time also without final conclusion.Closed cycle
Scheme, be by spentnuclear fuel uranium and plutonium recycling, then be made plutonium, uranium mixing mox fuel, be subsequently placed in reactor and carry out core
Reaction.This both can be reduced the long-lived radioactivity product in spentnuclear fuel, can also make full use of uranium and plutonium resource in spentnuclear fuel.
The spentnuclear fuel processing scheme that China's future will take is closed cycle scheme.Closed cycle scheme using transmuting come
Handle the long-life time actinium series nucleic in spentnuclear fuel.Transmuting refers to that long-life height is put nucleic carries out neutron photograph in neutron field
It penetrates, long-life height is put after the nuclear reactions such as fission, capture occur for nucleic and is converted to other short lives or stable nucleic, to disappear
Harm except Long-lived Radionuclides to ecological environment.
The most commonly used is mox fuel components for closed cycle scheme, it is the component being made of fuel rod and guide pipe.Fuel rod
By PuO2(plutonium oxide) and UO2(urania) mixes, and effect is that fission occurs to provide energy.In 17 × 17 fuel
In component, for physical parameters measurement using using, the effect of remaining 24 guide pipe is to provide control rod and plugs in the guide pipe at center
The space entered.The type that mox fuel component includes has 17 × 17 components for presurized water reactor, also there is the hexagonal groups for fast reactor
Part.
Fig. 1 is the schematic diagram of the mox fuel component of existing 17 × 17 array comprising 264 fuel rods and 25 lead
Xiang Guan, they constitute 17 × 17 quadrate array.Wherein 1 guide pipe occupies the center of array, other 24 guiding
Pipe radiates arrangement relative to the guide pipe at the center, is spaced 2 fuel rods substantially between adjacent two guide pipes.
Specifically, rectangular coordinate system, X-axis, the Y-axis of coordinate system are established by origin of the center of 17 × 17 quadrate array
It is parallel to the side of quadrate array, line space, the column pitch for defining 17 × 17 quadrate array are 1.So, there are 16 institutes
Guide pipe is stated to be located in four quadrants of coordinate system, their coordinate is (± 3, ± 3), (± 6, ± 3), (± 3, ± 6) and (±
5, ± 5), remaining 9 guide pipes are located at origin, at (± 3,0) and (± 6,0) position.264 fuel rods then occupy battle array
Remaining 264 coordinate positions in column.After arranging in the manner described above, the every guide pipe is adjacent with 8 fuel rods.
Currently, the transmuting facility that can provide neutron source in closed cycle scheme includes thermal-neutron reactor, fast neutron reactor and accelerates
The subcritical assembly (ADS) of device driving and other neutron sources etc..Wherein technology it is most mature, be thermal neutron running most heap-type
Presurized water reactor in heap, therefore the research for carrying out presurized water reactor transmuting technology is of great significance.In conjunction with the strategy of closed cycle, now
The scheme mainly considered is that long-life time actinium series nucleic is uniformly added in uranium oxide fuel presurized water reactor.And mox fuel is weary combustion
The aftertreatment products of material, doping long-life time actinium series nucleic are more easy.Meanwhile it only being adulterated in the mox fuel stick of part long-lived
Time actinium series nucleic is ordered, can make in component that changed power is more gentle, is more advantageous to the safe operation of reactor core.
Summary of the invention
Based on this, the object of the present invention is to provide a kind of mox fuel component for transmuting and flattening power, tools
There are transmuting time actinium series nucleic and flattening mox fuel component power.
A kind of mox fuel component for transmuting and flattening power, including doping fuel rod, fuel rod and guide pipe, institute
Stating doping fuel rod is the fuel rod for adulterating long-life time actinium series nucleic；It the doping fuel rod, the fuel rod and described leads
To pipe forming array, each doping fuel rod is adjacent with a guide pipe.
It is of the present invention for transmuting and to flatten the mox fuel component of power, by the part adjacent with guide pipe or
Whole fuel rods are set as doping fuel rod, and adulterating the long-life time actinium series nucleic in fuel rod in neutron field is short by transmuting
Service life or stable nucleic can solve the long-life time in spentnuclear fuel to reduce the cost and difficulty of spentnuclear fuel final process
The processing problem of actinium series nucleic.In addition, the mox fuel component for transmuting and flattening power of the invention includes long-life time actinium
It is that the doping fuel rod of nucleic doping adulterates the fission reaction rate of fuel rod while doping fuel rod reacts in reactor
It is weakened, to reduce in mox fuel component around guide pipe higher power originally, to reach flattening mox fuel component
Power, the effect for enhancing reactor core safety.
Further, symmetry axis and center of the distribution of the doping fuel rod and guide pipe relative to mox fuel component
It is symmetrical.Doping fuel rod is symmetric, and is conducive to the power for flattening mox fuel component on the whole.
Further, for the mox fuel component of 17 × 17 arrays, the quantity of the doping fuel rod is at 32~152
Between.Mox fuel component includes an appropriate number of doping fuel rod, not only improves the power flattening of mox fuel component, and advantageous
In the efficient transmuting of long-life time actinium series nucleic.
Further, the doping fuel rod is only to adulterate long-life time actinium series nucleic237The fuel rod of Np；The longevity
Order time actinium series nucleic237The mass percent that Np accounts for the doping fuel rod is 0.5%~3%.Doping237The concentration of Np is too low,
It cannot then achieve the effect that weaken fuel rod fission reaction rate, and handle the long-life time actinium series nucleic low efficiency in spentnuclear fuel；
Doping237The concentration of Np is too high, then the fission reaction rate for adulterating fuel rod is too low, influences normal reactor operation；Adulterate quality hundred
Divide than being 0.5%~3%237Np can suitably weaken the fission reaction rate of fuel rod, be conducive to flatten mox fuel component function
Rate.
Further, the doping fuel rod is doping long-life time actinium series nucleic237Np、241Am and243The fuel rod of Am；
The long-life time actinium series nucleic237Np、241Am and243The sum of Am three accounts for the mass percent for adulterating fuel rod
0.5%~3%.Adulterating gross mass percentage is 0.5%~3%237Np、241Am and243Am can suitably weaken splitting for fuel rod
Become reactivity, is conducive to flatten mox fuel component power.
Further, in the doping fuel rod, the long-life time actinium series nucleic of doping237Np、241Am and243Am three it
Between mass ratio be.The nucleic type and ratio are
Long-life time actinium series nucleic in spentnuclear fuel after discharging is 10 years cooling when 1000MW electrical power reactor burnup reaches 33MWd/kg
Situation, this is conducive to these three long-lives time actinium series nucleic in the spentnuclear fuel of unified transmuting reactor.
Further, the doping fuel rod is doping long-life time actinium series nucleic237Np、241Am、243Am、244Cm and245The fuel rod of Cm；The long-life time actinium series nucleic237Np、241Am、243Am、244Cm and245The sum of Cm accounts for the doping
The mass percent of fuel rod is 0.5%~3%.Adulterating gross mass percentage is 0.5%~3%237Np、241Am、243Am
、244Cm and245Cm can suitably weaken the fission reaction rate of fuel rod, be conducive to flatten mox fuel component power.
Further, in the doping fuel rod, the long-life time actinium series nucleic of doping237Np、241Am、243Am、244Cm
With245Mass ratio between Cm is .The nucleic type and ratio are that 1000MW electrical power reactor burnup reaches
When 33MWd/kg after discharging cooling 10 years in spentnuclear fuel long-life time actinium series nucleic situation, this is conducive to unified transmuting reactor
Spentnuclear fuel in this five kinds time actinium series nucleic.
In addition, the present invention also provides a kind of methods for flattening mox fuel component power.
A method of the adjacent fuel rod of the guide pipe of mox fuel group is replaced with and is mixed by flattening mox fuel component power
Miscellaneous fuel rod；The doping fuel rod is the fuel rod for adulterating long-life time actinium series nucleic.
The method of flattening mox fuel component power of the present invention utilizes the long-life time actinium series in doping fuel rod
Nucleic in neutron field by transmuting, to weaken the fission reaction rate of doping fuel rod, to reduce guide pipe week in mox fuel component
Higher power originally is enclosed, to achieve the effect that the power, the enhancing reactor core safety that flatten mox fuel component.
In order to better understand and implement, the invention will now be described in detail with reference to the accompanying drawings.
Detailed description of the invention
Fig. 1 is the schematic diagram of the mox fuel component of existing 17 × 17 array；
Fig. 2 is the schematic diagram of the mox fuel component of 17 × 17 arrays of the present invention comprising 32 doping fuel rods；
Fig. 3 is the schematic diagram of the mox fuel component of 17 × 17 arrays of the present invention comprising 92 doping fuel rods；
Fig. 4 is the schematic diagram of the mox fuel component of 17 × 17 arrays of the present invention comprising 152 doping fuel rods.
Specific embodiment
Mox fuel component for transmuting and flattening power of the invention, including doping fuel rod, fuel rod and guiding
Pipe, the doping fuel rod is the fuel rod for adulterating long-life time actinium series nucleic；The doping fuel rod, the fuel rod and institute
Guide pipe forming array is stated, the guide pipe is dispersed in the array, the doping fuel rod and the guide pipe phase
It is adjacent.
It is short life or stable nucleic by transmuting that the long-life time actinium series nucleic in fuel rod, which is adulterated, in neutron field, from
And reduce the cost and difficulty of spentnuclear fuel final process, it can solve the processing problem of the long-life time actinium series nucleic in spentnuclear fuel.
Due to the effect of moderator, the Moderation of the fast neutrons that fission reaction is generated is thermal neutron.In general, neutron and original after slowing down
Daughter nucleus reactivity is higher, for example,239The thermal-neutron fission cross-section of the easily fissioning nucleus such as Pu is bigger than fast cross section, to make to be located at
The power of fuel rod around the guide pipe of mox fuel component is higher, causes reactor capability uneven, further flattens power
Can making reactor operation, the safety is improved.Some or all of fuel rod around guide pipe is replaced with doping combustion by the present invention
Charge bar absorbs neutron by transmuting, to weaken doping combustion using the long-life time actinium series nucleic in doping fuel rod in neutron field
The fission reaction rate of charge bar, to reduce in mox fuel component around guide pipe higher power originally, to reach flattening MOX
The power of fuel assembly, the effect for enhancing reactor core safety.
The mox fuel component of common 17 × 17 array of model of mox fuel component.The present invention is with 17 × 17 arrays
For mox fuel component, on the basis of the mox fuel component of existing 17 × 17 array, by least 1 adjacent with guide pipe
Fuel rod replaces with doping fuel rod and obtains.
Fig. 2 is the schematic diagram of the mox fuel component of 17 × 17 arrays of the present invention comprising 32 doping fuel rods.It can be with
It obtains in the following way, selects coordinate to be located at the guide pipe of (3,3), (5,5), (3,6) and (6,3), by this 4 guide pipe weeks
8 fuel rods positioned at (4,3), (3,4), (5,3), (3,5), (5,4), (4,5), (6,4) and (4,6) enclosed replace with doping
Fuel rod；Then it will also be replaced with above-mentioned 8 doping fuel rods relative to the fuel rod on X-axis, Y-axis, origin symmetry position
Adulterate fuel rod to get to Fig. 2 by (± 4, ± 3), (± 3, ± 4), (± 5, ± 3), (± 3, ± 5), (± 5, ± 4), (± 4,
± 5), 32 fuel rods at (± 6, ± 4) and (± 4, ± 6) coordinate replace with the arrangement mode of doping fuel rod.
Similarly, Fig. 3 is the signal of the mox fuel component of 17 × 17 arrays of the present invention comprising 92 doping fuel rods
Figure.It can be obtained in the following way, and 19 fuel rods in total in first quartile around guide pipe are replaced with doping combustion
Charge bar, 19 doping fuel rod are symmetrical relative to the bisector of X-axis and Y-axis；It then will be with 19 doping fuel rod
Doping fuel rod is also replaced with relative to the fuel rod on X-axis, Y-axis, origin symmetry position；Finally by (± 1,0) in X-axis, (±
2,0), (± 4,0), 8 fuel rods on (± 5,0) position, (0, ± 1), (0, ± 2), (0, ± 4) and (0, ± 5) position in Y-axis
8 fuel rods set replace with doping fuel rod all to get the arrangement mode of Fig. 3 is arrived.
Similarly, Fig. 4 is the signal of the mox fuel component of 17 × 17 arrays of the present invention comprising 152 doping fuel rods
Figure.It is obtained in the following way, and 33 fuel rods in total in first quartile around guide pipe are replaced with doping fuel rod,
33 doping fuel rod is symmetrical relative to the bisector of X-axis and Y-axis；Then will with 33 doping fuel rods relative to
X-axis, Y-axis, the fuel rod on origin symmetry position also replace with doping fuel rod；Finally by (± 1,0) in X-axis, (± 2,0),
(0, ± 1) on 10 fuel rods, Y-axis on (± 4,0), (± 5,0) and (± 7,0) position, (0, ± 2), (0, ± 4), (0, ±
5) and 10 fuel rods on (0, ± 7) position replace with doping fuel rod all to get the arrangement mode of Fig. 4 is arrived.
Doping fuel rod of the invention is symmetrical, is conducive to the power for flattening mox fuel component on the whole.For 17 ×
The mox fuel component of 17 arrays replaces the quantity of fuel rod between 32~152.If the quantity for adulterating fuel rod is very little,
Then to reach actinium series nucleic efficiency of same transmuting long-life time, high concentration long-life time Excitation Bands must be carried out to doping fuel rod
Element doping, and then cause the fission reaction rate for adulterating fuel rod too low, influence the normal operation of reactor；Simultaneously as mixing
Miscellaneous fuel rod fission reaction rate is lower than minimum fission reaction rate in former mox fuel component, leads to not flatten power even increase
The inhomogeneities of power distribution；The quantity for adulterating fuel rod is too many, then being equivalent to all fuel rods is doping fuel rod, is caused
Doping fuel rod cannot play a part of to flatten mox fuel component power.
It is noted that other replace fuel rod quantity between 32~152 other than the alternative of Fig. 2-4, and
Fuel rod is adulterated after replacement relative to all symmetrical alternative of origin, X-axis and Y-axis, can equally play 17 × 17 array of flattening
Mox fuel component power effect.
Doping fuel rod of the present invention, the actinium series nucleic of total long-life time of incorporation account for the quality hundred of the doping fuel rod
Divide than being 0.5%~3%.If long-life time actinium series nucleic doping is too low, it cannot reach and weaken fuel rod fission reaction rate
Effect, and handle the low efficiency of long-life time actinium series nucleic；If long-life time actinium series nucleic doping is too high, fuel is adulterated
Stick fission reaction rate is too low, influences normal reactor operation.In the present invention, the specific doping way of the doping fuel rod has three
Kind:
1, it only adulterates237Np。
2, it adulterates237Np、241Am and243Am, wherein the mass ratio between three be .The nucleic type and ratio, when being that 1000MW electrical power reactor burnup reaches 33MWd/kg
After discharging cooling 10 years in spentnuclear fuel long-life time actinium series nucleic situation, doping in this way can reduce the difficulty that spentnuclear fuel post-processes
Degree, such as considers the spentnuclear fuel that the reactor of other power is generated in other burnups, this ratio can also change.
3, it adulterates237Np、241Am、243Am、244Cm and245Cm, wherein the mass ratio between five is.It should
Nucleic type and ratio are secondary in spentnuclear fuel after discharging cooling 10 years when 1000MW electrical power reactor burnup reaches 33MWd/kg
Actinium series nucleic situation (244The half-life period of Cm is 18 years, is not long lived nuclides, and being considered together here is because individually making it
Separation increases cost), doping in this way can reduce the difficulty of spentnuclear fuel post-processing, such as consider the reactor of other power at other
The spentnuclear fuel generated when burnup, this ratio can also change.
Below by taking the mox fuel component of 17 × 17 array shown in Fig. 3 as an example, illustrate technical effect of the invention.
The power distribution of the mox fuel component of existing 17 × 17 array is calculated, calculated result be listed in Table 1 below the
A line.
Example 1 calculates the power distribution of the mox fuel component for 17 × 17 arrays that fuel rod is adulterated containing 92,
Wherein the plutonium content of every fuel rod and doping fuel rod is 9.8%, and the doping fuel rod is that incorporation mass percent is
3%237The fuel rod of Np, the second row that calculated result is listed in Table 1 below.
Example 2 calculates the power distribution of the mox fuel component for 17 × 17 arrays that fuel rod is adulterated containing 92,
Wherein the plutonium content of every fuel rod and doping fuel rod is 9.8%；The doping fuel rod is that incorporation mass percent is
The fuel rod of 3% long-life time actinium series nucleic, the type and mass ratio of the long-life time actinium series nucleic of the incorporation are , meter
Calculate the third line that the results are shown in Table 1.
Table 1
Calculation shows that is, (burnup is to measure the release of unit mass heavy metal gross energy in nuclear fuel to burnup in beginning of life
Amount) when being 0MWd/kg, the variance of all fuel rods (fuel rod and doping fuel rod) power of invention components, power are most
The accordingly result of the ratio between big value and minimum value both less than existing mox fuel component.In the end of term in longevity, i.e., when burnup is 50MWd/kg,
The ratio between all fuel rod burnup variances of invention components, maxima and minima both less than existing mox fuel component it is corresponding
As a result.It can be seen that the power distribution of mox fuel component of the invention is all either during beginning of life or whole service
It is more smoother than existing mox fuel component.
In addition, calculation shows that, in average burn-up 50MWd/kg, there are about 47% in example 1237Np is by transmuting, in example 2 about
There is 55% long-life time actinium series nucleic by the transmuting (longevity that mox fuel component itself generates when need to consider to undope when calculating
Order time actinium series nucleic).
It can be seen that some or all of fuel rod around guide pipe is replaced with doping fuel rod by the present invention, doping
Long-life time actinium series nucleic in fuel rod is short life or stable nucleic by transmuting in neutron field, to reduce spentnuclear fuel
The cost and difficulty of final process can solve the processing problem of the long-life time actinium series nucleic in spentnuclear fuel.In addition, of the invention
Mox fuel component for transmuting and flattening power includes the doping fuel rod of long-life time actinium series nucleic doping, adulterates fuel
While stick reacts in reactor, the fission reaction rate for adulterating fuel rod is weakened, to reduce guide pipe in mox fuel component
The higher power of surrounding script, to achieve the effect that the power, the enhancing reactor core safety that flatten mox fuel component.
The embodiments described above only express several embodiments of the present invention, and the description thereof is more specific and detailed, but simultaneously
It cannot therefore be construed as limiting the scope of the patent.It should be pointed out that coming for those of ordinary skill in the art
It says, without departing from the inventive concept of the premise, various modifications and improvements can be made, these belong to protection of the invention
Range.
Claims (9)
1. a kind of mox fuel component for transmuting and flattening power, including fuel rod and guide pipe, it is characterised in that: also wrap
Doping fuel rod is included, the doping fuel rod is doping long-life time actinium series nucleic237Np、241Am、243Am、244Cm and245In Cm
One or more of fuel rods；The doping fuel rod, the fuel rod and the guide pipe forming array, each doping combustion
Charge bar is adjacent with a guide pipe.
2. the mox fuel component according to claim 1 for transmuting and flattening power, it is characterised in that: the doping
The distribution of fuel rod and guide pipe is symmetrical relative to the symmetry axis of mox fuel component and center.
For transmuting and the mox fuel component of power is flattened 3. according to claim 1, it is characterised in that: for 17 ×
The mox fuel component of 17 arrays, the quantity of the doping fuel rod is between 32~152.
4. the mox fuel component described in any one of -3 claims for transmuting and flattening power according to claim 1,
It is characterized by: the doping fuel rod is only to adulterate long-life time actinium series nucleic237The fuel rod of Np；The long-life time actinium
It is nucleic237The mass percent that Np accounts for the doping fuel rod is 0.5%~3%.
5. the mox fuel component described in any one of -3 claims for transmuting and flattening power according to claim 1,
It is characterized by: the doping fuel rod is doping long-life time actinium series nucleic237Np、241Am and243The fuel rod of Am；The length
Service life time actinium series nucleic237Np、241Am and243The sum of Am three account for it is described doping fuel rod mass percent be 0.5%~
3%.
6. the mox fuel component according to claim 5 for transmuting and flattening power, it is characterised in that: mixed described
In miscellaneous fuel rod, the long-life time actinium series nucleic of doping237Np、241Am and243Mass ratio between Am three is
7. the mox fuel component described in any one of -3 claims for transmuting and flattening power according to claim 1,
It is characterized by: the doping fuel rod doping long-life time actinium series nucleic237Np、241Am、243Am、244Cm and245Cm；The length
Service life time actinium series nucleic237Np、241Am、243Am、244Cm and245The sum of Cm accounts for the mass percent for adulterating fuel rod
0.5%~3%.
8. the mox fuel component according to claim 7 for transmuting and flattening power, it is characterised in that: mixed described
In miscellaneous fuel rod, the long-life time actinium series nucleic of doping237Np、241Am、243Am、244Cm and245Mass ratio between Cm is
9. a kind of method for flattening mox fuel component power, it is characterised in that: by the adjacent fuel of the guide pipe of mox fuel group
Stick replaces with doping fuel rod；The doping fuel rod is doping long-life time actinium series nucleic237Np、241Am、243Am、244Cm
With245The fuel rod of one or more of Cm.
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| CN108550405A (en) * | 2018-03-23 | 2018-09-18 | 中山大学 | Mox fuel stick, mox fuel component and the method for flattening axial power |
| CN108470589B (en) * | 2018-05-02 | 2024-05-17 | 中国科学技术大学 | Fast-heating mixed energy spectrum critical reactor core capable of simultaneously transmuting minor actinides and long-service-life fission products |
| CN109036592A (en) * | 2018-06-12 | 2018-12-18 | 中山大学 | Doping fuel-involucrum combination for transmuting |
| CN110706829B (en) * | 2019-10-18 | 2021-05-07 | 中国科学院合肥物质科学研究院 | Integrated compact reactor core with radial power flattening function |
| CN112599259B (en) * | 2020-11-27 | 2023-11-24 | 中国核电工程有限公司 | Fusion-fission hybrid reactor transmutation fuel assembly |
| CN113593730B (en) * | 2021-07-12 | 2023-08-29 | 西南科技大学 | Heterogeneous MA transmutation rod for fast neutron reactor |
| CN113643838B (en) * | 2021-07-27 | 2023-08-11 | 西南科技大学 | Heterogeneous MA transmutation rod with flattening reactor core axial power function |
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