CN107093467A - Method for the mox fuel component and flattening power of transmuting and flattening power - Google Patents
Method for the mox fuel component and flattening power of transmuting and flattening power Download PDFInfo
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- CN107093467A CN107093467A CN201710193424.8A CN201710193424A CN107093467A CN 107093467 A CN107093467 A CN 107093467A CN 201710193424 A CN201710193424 A CN 201710193424A CN 107093467 A CN107093467 A CN 107093467A
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- 239000000446 fuel Substances 0.000 title claims abstract description 241
- 238000000034 method Methods 0.000 title claims abstract description 17
- 150000001257 actinium Chemical class 0.000 claims abstract description 52
- 238000003491 array Methods 0.000 claims description 13
- 229910052767 actinium Inorganic materials 0.000 claims description 6
- QQINRWTZWGJFDB-UHFFFAOYSA-N actinium atom Chemical compound [Ac] QQINRWTZWGJFDB-UHFFFAOYSA-N 0.000 claims description 6
- 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 11
- 230000008569 process Effects 0.000 abstract description 9
- 238000010586 diagram Methods 0.000 description 6
- 229910052778 Plutonium Inorganic materials 0.000 description 5
- 238000002485 combustion reaction Methods 0.000 description 5
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 5
- 241000894007 species Species 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
- 238000012545 processing Methods 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 239000000463 material Substances 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 238000005728 strengthening Methods 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
- 230000009286 beneficial effect Effects 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
- 238000001816 cooling 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
- 238000011160 research Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 0.000 description 1
- 230000003313 weakening effect Effects 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 present invention relates to a kind of method of mox fuel component and flattening power for transmuting and flattening 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 for doping long-life time actinium series nucleic fuel rod；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 to long-life time actinium series nucleic in the fuel rod that adulterates, doping fuel rod in neutron field by transmuting, so as to reduce the cost and difficulty of spentnuclear fuel final process for transmuting and the mox fuel component of flattening power by the present invention.Meanwhile, the fission reaction rate of doping fuel rod is weakened, to reduce power originally higher around guide pipe in mox fuel component, so as to reach the power of flattening mox fuel component, strengthen the effect of reactor core security.
Description
Technical field
It is more particularly to a kind of that there is transmuting Ci Actinium system's nucleic and flattening power work(the present invention relates to nuclear engineering technical field
The mox fuel component of energy.
Background technology
With the rapid growth of China's economy, the demand to the energy is greatly increased, particularly after signature Paris agreement,
Develop green energy resource turns into the most important thing.The characteristics of nuclear energy has efficient, cleaning and is stable, its energy for meeting China is needed
Ask.In recent years, China's pressurized-water reactor nuclear power plant rapid growth, but the spentnuclear fuel accumulation therefore produced also quickly increases.These are weary
Fuel lifetime length, radiotoxicity are big, the living environment of the long-term threat mankind.
Half-life period longer Actinium systems nucleic in spentnuclear fuel process problem, especially spentnuclear fuel237Np、241Am、243Am、244Cm and245Cm process problem, is long-standing problem people and there is the problem largely disputed on.In face of this severe situation,
How to deal carefully with, dispose spentnuclear fuel, be one to ensure the Environmental security of descendants and the sustainable development of China's nuclear energy
The significant problem that must be solved.At present, the processing in the world to spentnuclear fuel mainly has two schemes.One kind is using the U.S. as representative
Open circulation scheme, another is the closed cycle scheme using European Union as representative.Open circulation scheme is landfill, is by weary combustion
Material wraps up directly buried in underground after in a few years cooling down, then with glass or concrete.But containing higher in spentnuclear fuel
Fissionable isotope, directly landfill can not make full use of these fissible resources；Further, since gradation actinium series in the middle part of spentnuclear fuel
The half-life period of element is very long, and whether the container of parcel spentnuclear fuel can bear the sufficiently long time also without final conclusion.Closed cycle
Scheme, is to reclaim the uranium in spentnuclear fuel and plutonium, then plutonium, the mox fuel of uranium mixing is made, and is subsequently placed in reactor and carries out core
Reaction.This can reduce the long-lived radioactivity product in spentnuclear fuel, can also make full use of the uranium and plutonium resource in spentnuclear fuel.
The spentnuclear fuel processing scheme that China will take in future is closed cycle scheme.Closed cycle scheme using transmuting come
Handle the long-life Ci Actinium systems nucleic in spentnuclear fuel.Transmuting refers to that long-life height is put into nucleic carries out neutron photograph in neutron field
Penetrate, long-life height puts nucleic and occurs to be converted to other short lives or stable nucleic after the nuclear reactions such as fission, capture, so as to disappear
Harm except Long-lived Radionuclides to ecological environment.
What closed cycle scheme was commonly used is mox fuel component, and it is the component being made up of fuel rod and guide pipe.Fuel rod
By PuO2(plutonium oxide) and UO2(urania) is mixed, and it is to occur fission to provide energy that it, which is acted on,.In 17 × 17 fuel
In component, the guide pipe of center is for physical parameters measurement using using, and the effect of remaining 24 guide pipe is to provide control rod and inserted
The space entered.The type that mox fuel component is included has 17 × 17 to be used for the component of 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, and it includes 264 fuel rods and 25 are led
Xiang Guan, they constitute 17 × 17 quadrate array.Wherein 1 guide pipe occupies the center of array, other 24 guiding
Pipe radiates relative to the guide pipe of the center and is spaced 2 fuel rods between arrangement, adjacent two guide pipes substantially.
Specifically, rectangular coordinate system, X-axis, the Y-axis of coordinate system are set up by origin of the center of 17 × 17 quadrate array
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
State guide pipe positioned at coordinate system four quadrants in, their coordinate for (± 3, ± 3), (± 6, ± 3), (± 3, ± 6) and (±
5, ± 5), remaining 9 guide pipes are at origin, (± 3,0) and (± 6,0) position.264 fuel rods then occupy battle array
Remaining 264 coordinate positions in row.After arranging in the manner described above, the every guide pipe is adjacent with 8 fuel rods.
Currently, the transmuting facility of neutron source can be provided in closed cycle scheme to be included thermal-neutron reactor, fast neutron reactor and accelerates
Subcritical assembly (ADS) and other neutron sources of device driving etc..Wherein technology it is most ripe, be thermal neutron running most heap-type
Presurized water reactor in heap, therefore it is significant to carry out the research of presurized water reactor transmuting technology.With reference to the strategy of closed cycle, now
The scheme mainly considered is the uniform addition long-life time actinium series nucleic 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 is more easy.Meanwhile, only adulterated in the mox fuel rod of part long-lived
Life time actinium series nucleic, can make in component that changed power is more gentle, be more beneficial for the safe operation of reactor core.
The content of the invention
Based on this, it is an object of the present invention to provide a kind of for transmuting and the mox fuel component of flattening power, it has
There are transmuting Ci Actinium system's nucleic and flattening mox fuel component power.
It is a kind of to be used for the mox fuel component of transmuting and flattening power, including doping fuel rod, fuel rod and guide pipe, institute
State fuel rod of the doping fuel rod for doping long-life time actinium series nucleic；The doping fuel rod, the fuel rod and described lead
To pipe forming array, each doping fuel rod is adjacent with a guide pipe.
It is of the present invention for transmuting and the mox fuel component of flattening power, by the part adjacent with guide pipe or
The long-life time actinium series nucleic that whole fuel rods are set in the fuel rod that adulterates, doping fuel rod is short by transmuting in neutron field
Life-span or stable nucleic, so as to reduce the cost and difficulty of spentnuclear fuel final process, can solve the long-life time in spentnuclear fuel
The process problem of actinium series nucleic.In addition, the be used for transmuting and the mox fuel component of flattening power of the present invention include long-life time actinium
It is the doping fuel rod of nucleic doping, while doping fuel rod reacts in reactor, the fission reaction rate for the fuel rod that adulterates
It is weakened, to reduce power originally higher around guide pipe in mox fuel component, so as to reach flattening mox fuel component
Power, the effect for strengthening reactor core security.
Further, the doping fuel rod and symmetry axis of the distribution relative to mox fuel component of guide pipe and center
It is symmetrical.Doping fuel rod is symmetric, and is conducive to flattening the power of 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 favorably
In the efficient transmuting of long-life time actinium series nucleic.
Further, the doping fuel rod is only doping long-life time actinium series nucleic237Np fuel rod；The longevity
Life time actinium series nucleic237The mass percent that Np accounts for the doping fuel rod is 0.5%~3%.Doping237Np concentration is too low,
It can not then reach that the long-life time actinium series nucleic efficiency in the effect for weakening fuel rod fission reaction rate, and processing spentnuclear fuel is low；
Doping237Np concentration is too high, then the fission reaction rate for the fuel rod that adulterates is too low, influences normal reactor operation；Doping quality hundred
Divide than being 0.5%~3%237Np, can suitably weaken the fission reaction rate of fuel rod, be conducive to flattening mox fuel component work(
Rate.
Further, the doping fuel rod is doping long-life time actinium series nucleic237Np、241Am and243Am fuel rod；
The long-life time actinium series nucleic237Np、241Am and243Am three's sum accounts for the mass percent for adulterating fuel rod
0.5%~3%.Gross mass of adulterating percentage is 0.5%~3%237Np、241Am and243Am, can suitably weaken splitting for fuel rod
Become reactivity, be conducive to flattening 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 species and ratio, be
Long-life time actinium series nucleic in spentnuclear fuel after discharging is cooled down 10 years when 1000MW electrical power reactor burnups reach 33MWd/kg
Situation, this is conducive to these three long-lives time actinium series nucleic in the uniformly spentnuclear fuel of transmuting reactor.
Further, the doping fuel rod is doping long-life time actinium series nucleic237Np、241Am、243Am、244Cm and245Cm fuel rod；The long-life time actinium series nucleic237Np、241Am、243Am、244Cm and245Cm sums account for the doping
The mass percent of fuel rod is 0.5%~3%.Gross mass of adulterating percentage is 0.5%~3%237Np、241Am、243Am
、244Cm and245Cm, can suitably weaken the fission reaction rate of fuel rod, be conducive to flattening 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 species and ratio, are after discharging is cooled down 10 years when 1000MW electrical power reactor burnups reach 33MWd/kg in spentnuclear fuel
The situation of long-life time actinium series nucleic, this is conducive to this five kinds actinium series nucleic in the uniformly spentnuclear fuel of transmuting reactor.
In addition, present invention also offers a kind of method for flattening mox fuel component power.
A kind of method for flattening mox fuel component power, the adjacent fuel rod of the guide pipe of mox fuel group is replaced with and mixed
Miscellaneous fuel rod；The doping fuel rod is the fuel rod of doping 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 the fuel rod that adulterates
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
Originally higher power is enclosed, so as to reach the power of flattening mox fuel component, strengthen the effect of reactor core security.
In order to more fully understand and implement, the invention will now be described in detail with reference to the accompanying drawings.
Brief description of the drawings
Fig. 1 is the schematic diagram of the mox fuel component of existing 17 × 17 array；
Fig. 2 includes the schematic diagram of the mox fuel component of 17 × 17 arrays of 32 doping fuel rods for the present invention；
Fig. 3 includes the schematic diagram of the mox fuel component of 17 × 17 arrays of 92 doping fuel rods for the present invention；
Fig. 4 includes the schematic diagram of the mox fuel component of 17 × 17 arrays of 152 doping fuel rods for the present invention.
Embodiment
The present invention's is used for the mox fuel component of transmuting and flattening power, including doping fuel rod, fuel rod and guiding
Pipe, the doping fuel rod is the fuel rod of doping 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.
The long-life time actinium series nucleic in fuel rod that adulterates is short life or stable nucleic by transmuting in neutron field, from
And reduce the cost and difficulty of spentnuclear fuel final process, the process problem of the long-life time actinium series nucleic in spentnuclear fuel can be solved.
Due to the effect of moderator, the Moderation of the fast neutrons that fission reaction is produced is thermal neutron.In general, neutron and original after slowing down
Daughter nucleus reactivity is higher, such as,239The thermal-neutron fission cross-section of the easily fissioning nucleus such as Pu is bigger than fast cross section, so that being 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 improve the security of reactor operation.The some or all of fuel rod that the present invention is directed to around pipe replaces with doping combustion
Charge bar, absorbs neutron by transmuting, to weaken doping combustion using the long-life time actinium series nucleic in the fuel rod that adulterates in neutron field
The fission reaction rate of charge bar, to reduce power originally higher around guide pipe in mox fuel component, so as to reach flattening MOX
The power of fuel assembly, the effect for strengthening reactor core security.
The mox fuel component of the common array of model 17 × 17 of mox fuel component.The present invention is with 17 × 17 arrays
Exemplified by 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 obtained.
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
Obtain in the following way, selection coordinate is 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 will also it be replaced with relative to the fuel rod on X-axis, Y-axis, origin symmetry position with above-mentioned 8 doping fuel rods
Adulterate fuel rod, that is, obtain Fig. 2 will (± 4, ± 3), (± 3, ± 4), (± 5, ± 3), (± 3, ± 5), (± 5, ± 4), (± 4,
± 5), (± 6, ± 4) and (± 4, ± 32 fuel rods 6) at 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 altogether in first quartile around guide pipe are replaced with into doping combustion
Charge bar, 19 doping fuel rod is symmetrical relative to the bisector of X-axis and Y-axis；Then will be with described 19 doping fuel rods
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, in Y-axis (0, ± 1), (0, ± 2), (0, ± 4) and (0, ± 5) position
8 fuel rods put all replace with doping fuel rod, that is, obtain Fig. 3 arrangement mode.
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 altogether in first quartile around guide pipe are replaced with into doping fuel rod,
33 doping fuel rod is symmetrical relative to the bisector of X-axis and Y-axis；Then will with described 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),
On 10 fuel rods, Y-axis on (± 4,0), (± 5,0) and (± 7,0) position (0, ± 1), (0, ± 2), (0, ± 4), (0, ±
And (0, ± 10 fuel rods 7) on position all replace with doping fuel rod, that is, obtain Fig. 4 arrangement mode 5).
The doping fuel rod of the present invention is symmetrical, is conducive to flattening the power of 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 the fuel rod that adulterates is very little,
Actinium series nucleic efficiency of same transmuting long-life time is then reached, high concentration long-life time Excitation Bands must be carried out to doping fuel rod
Element doping, and then cause the fission reaction rate of doping fuel rod too low, influence the normal operation of reactor；Simultaneously as mixing
Miscellaneous fuel rod fission reaction rate is less than minimum fission reaction rate in former mox fuel component, leads to not flattening power or even increases
The inhomogeneities of power distribution；The quantity of doping fuel rod is too many, then is doping fuel rod equivalent to all fuel rods, causes
Doping fuel rod can not play a part of to flatten mox fuel component power.
It is noted that in addition to Fig. 2-4 substitute mode, other replace fuel rod quantity between 32~152, and
Fuel rod is adulterated after replacement relative to all symmetrical substitute mode of origin, X-axis and Y-axis, the array of flattening 17 × 17 can be equally played
Mox fuel component power effect.
Doping fuel rod of the present invention, the actinium series nucleic of total long-life time of incorporation accounts 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, decrease fuel rod fission reaction rate can not be reached
Effect, and the efficiency of processing long-life time actinium series nucleic is low；If long-life time actinium series nucleic doping is too high, adulterate fuel
Rod 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：
1st, only adulterate237Np。
2nd, adulterate237Np、241Am and243Mass ratio between Am, wherein three is .The nucleic species and ratio, when being that 1000MW electrical power reactor burnups reach 33MWd/kg
Discharging cool down 10 years after in spentnuclear fuel long-life time actinium series nucleic situation, so doping can reduce the difficulty that spentnuclear fuel is post-processed
Degree, such as considers the spentnuclear fuel that the reactor of other power is produced in other burnups, this ratio can also be changed.
3rd, adulterate237Np、241Am、243Am、244Cm and245Cm, wherein the mass ratio between five is.Should
Nucleic species and ratio, are after discharging is cooled down 10 years when 1000MW electrical power reactor burnups reach 33MWd/kg in spentnuclear fuel time
Actinium series nucleic situation (244Cm half-life period is 18 years, is not long lived nuclides, and it is because individually making it to be considered together here
Separation increase cost), so doping can reduce the difficulty of spentnuclear fuel post processing, such as consider the reactor of other power at other
The spentnuclear fuel produced during burnup, this ratio can also be changed.
Below by taking the mox fuel component of 17 × 17 arrays shown in Fig. 3 as an example, illustrate the technique effect of the present invention.
Power distribution to the mox fuel component of existing 17 × 17 array is calculated, result of calculation be listed in Table 1 below
A line.
Example 1, the power distribution to the mox fuel component of 17 × 17 arrays containing 92 doping fuel rods are calculated,
The plutonium content of wherein every fuel rod and doping fuel rod is 9.8%, and the doping fuel rod is that incorporation mass percent is
3%237Np fuel rod, the second row that result of calculation is listed in Table 1 below.
Example 2, the power distribution to the mox fuel component of 17 × 17 arrays containing 92 doping fuel rods are calculated,
The plutonium content of wherein 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 species 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
Calculating shows that (burnup is to weigh the release of unit mass heavy metal gross energy in nuclear fuel in beginning of life, i.e. burnup
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.When the end of term in longevity, i.e. burnup are 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.As can be seen here, either during beginning of life, or whole service, the power distribution of mox fuel component of the invention is all
It is more smoother than existing mox fuel component.
Show in addition, calculating, in average burn-up 50MWd/kg, 47% is there are about 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 is generated when need to consider to undope during calculating in itself
Life time actinium series nucleic).
As can be seen here, some or all of fuel rod that the present invention is directed to around pipe replaces with doping fuel rod, adulterates
Long-life time actinium series nucleic in fuel rod is short life or stable nucleic by transmuting in neutron field, so as to reduce spentnuclear fuel
The cost and difficulty of final process, can solve the process problem of the long-life time actinium series nucleic in spentnuclear fuel.In addition, the present invention
Mox fuel component for transmuting and flattening power includes the doping fuel rod of long-life time actinium series nucleic doping, and adulterate fuel
While rod reacts in reactor, the fission reaction rate of doping fuel rod is weakened, to reduce guide pipe in mox fuel component
The originally higher power of surrounding, so as to reach the power of flattening mox fuel component, strengthen the effect of reactor core security.
Embodiment described above only expresses the several embodiments of the present invention, and it describes more specific and detailed, but simultaneously
Can not therefore it be construed as limiting the scope of the patent.It should be pointed out that coming for one of ordinary skill in the art
Say, without departing from the inventive concept of the premise, various modifications and improvements can be made, these belong to the protection of the present invention
Scope.
Claims (9)
1. it is a kind of for transmuting and the mox fuel component of 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 the fuel rod of doping long-life time actinium series nucleic；The doping fuel rod, described
Fuel rod and the guide pipe forming array, each doping fuel rod are adjacent with a guide pipe.
2. it is according to claim 1 for transmuting and the mox fuel component of 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.
3. it is according to claim 1 for transmuting and the mox fuel component of flattening power, 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. it is used for the mox fuel component of transmuting and flattening power according to any one claim in claim 1-3,
It is characterized in that：The doping fuel rod is only doping long-life time actinium series nucleic237Np fuel rod；The long-life time actinium
It is nucleic237The mass percent that Np accounts for the doping fuel rod is 0.5%~3%.
5. it is used for the mox fuel component of transmuting and flattening power according to any one claim in claim 1-3,
It is characterized in that：The doping fuel rod is doping long-life time actinium series nucleic237Np、241Am and243Am fuel rod；The length
Life-span time actinium series nucleic237Np、241Am and243Am three's sum account for the mass percent of the doping fuel rod for 0.5%~
3%.
6. it is according to claim 5 for transmuting and the mox fuel component of 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. it is used for the mox fuel component of transmuting and flattening power according to any one claim in claim 1-3,
It is characterized in that：The doping fuel rod doping long-life time actinium series nucleic237Np、241Am、243Am、244Cm and245Cm；The length
Life-span time actinium series nucleic237Np、241Am、243Am、244Cm and245Cm sums account for the mass percent for adulterating fuel rod
0.5%~3%.
8. it is according to claim 7 for transmuting and the mox fuel component of 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
Rod replaces with doping fuel rod；The doping fuel rod is the fuel rod of doping long-life time actinium series nucleic.
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