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 PDF

Info

Publication number
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
Authority
CN
China
Prior art keywords
fuel
doping
fuel rod
mox
transmuting
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201710193424.8A
Other languages
Chinese (zh)
Other versions
CN107093467A (en
Inventor
袁岑溪
陈胜利
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
National Sun Yat Sen University
Original Assignee
National Sun Yat Sen University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by National Sun Yat Sen University filed Critical National Sun Yat Sen University
Priority to CN201710193424.8A priority Critical patent/CN107093467B/en
Publication of CN107093467A publication Critical patent/CN107093467A/en
Application granted granted Critical
Publication of CN107093467B publication Critical patent/CN107093467B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326Bundles 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
    • G21C3/328Relative disposition of the elements in the bundle lattice
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48Non-aqueous processes
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

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

The method of mox fuel component and flattening power for transmuting and flattening power
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.
CN201710193424.8A 2017-03-28 2017-03-28 The method of mox fuel component and flattening power for transmuting and flattening power Active CN107093467B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201710193424.8A CN107093467B (en) 2017-03-28 2017-03-28 The method of mox fuel component and flattening power for transmuting and flattening power

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201710193424.8A CN107093467B (en) 2017-03-28 2017-03-28 The method of mox fuel component and flattening power for transmuting and flattening power

Publications (2)

Publication Number Publication Date
CN107093467A CN107093467A (en) 2017-08-25
CN107093467B true CN107093467B (en) 2019-02-05

Family

ID=59646221

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201710193424.8A Active CN107093467B (en) 2017-03-28 2017-03-28 The method of mox fuel component and flattening power for transmuting and flattening power

Country Status (1)

Country Link
CN (1) CN107093467B (en)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
CN108470589A (en) * 2018-05-02 2018-08-31 中国科学技术大学 It is a kind of can transmuting simultaneously time actinium series nucleic and long-lived fission product the fast critical reactor core of hot mixing power spectrum
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

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6652661B2 (en) * 2001-10-12 2003-11-25 Bobolink, Inc. Radioactive decontamination and translocation method
CN1961380A (en) * 2004-05-28 2007-05-09 法国原子能委员会 Method for co-precipitation of actinides in different oxidation states and method for preparation of mixed actinide compounds
KR100963472B1 (en) * 2008-04-17 2010-06-17 한국원자력연구원 Metallic fuel rod in metal sheath including metallic fuel particles and a preparation method thereof
CN102376376A (en) * 2010-08-26 2012-03-14 中国核动力研究设计院 Reactor core design method for improving reactivity and transmutation effect of homogeneous spent fuel solution transmutation reactor
CN102831939A (en) * 2012-09-14 2012-12-19 南华大学 Nuclear fuel element doped with technetium-99
CN103093836A (en) * 2013-01-15 2013-05-08 西安交通大学 Fusion driving subcritical cladding of transmutation subordinate actinium series nuclide
CN103106939A (en) * 2013-01-15 2013-05-15 西安交通大学 Method of transmuting long-life high level radioactive nuclide through using pressurized water reactor
CN103827039A (en) * 2011-09-26 2014-05-28 原子能和替代能源委员会 Process for preparing an oxychloride and/or oxide of actinide(s) and/or of lanthanide(s) from a medium comprising at least one molten salt

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103093837A (en) * 2013-01-15 2013-05-08 西安交通大学 Accelerator-driven subcritical transmutation reactor core adopting dispersion metal fuel
CN103093839B (en) * 2013-01-22 2016-01-06 中科华核电技术研究院有限公司 The fuel assembly of light-water reactor
CN104952492B (en) * 2015-05-11 2017-08-01 中国核动力研究设计院 Carry gadolinia fuel rod and with the fuel assembly and pressurized water reactor core for carrying gadolinia fuel rod
CN105390167B (en) * 2015-11-05 2017-05-31 中国核动力研究设计院 A kind of supercritical water reactor fuel assembly and reactor core

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6652661B2 (en) * 2001-10-12 2003-11-25 Bobolink, Inc. Radioactive decontamination and translocation method
CN1961380A (en) * 2004-05-28 2007-05-09 法国原子能委员会 Method for co-precipitation of actinides in different oxidation states and method for preparation of mixed actinide compounds
KR100963472B1 (en) * 2008-04-17 2010-06-17 한국원자력연구원 Metallic fuel rod in metal sheath including metallic fuel particles and a preparation method thereof
CN102376376A (en) * 2010-08-26 2012-03-14 中国核动力研究设计院 Reactor core design method for improving reactivity and transmutation effect of homogeneous spent fuel solution transmutation reactor
CN103827039A (en) * 2011-09-26 2014-05-28 原子能和替代能源委员会 Process for preparing an oxychloride and/or oxide of actinide(s) and/or of lanthanide(s) from a medium comprising at least one molten salt
CN102831939A (en) * 2012-09-14 2012-12-19 南华大学 Nuclear fuel element doped with technetium-99
CN103093836A (en) * 2013-01-15 2013-05-08 西安交通大学 Fusion driving subcritical cladding of transmutation subordinate actinium series nuclide
CN103106939A (en) * 2013-01-15 2013-05-15 西安交通大学 Method of transmuting long-life high level radioactive nuclide through using pressurized water reactor

Also Published As

Publication number Publication date
CN107093467A (en) 2017-08-25

Similar Documents

Publication Publication Date Title
CN107093467B (en) The method of mox fuel component and flattening power for transmuting and flattening power
CN103106939B (en) Method of transmuting long-life high level radioactive nuclide through using pressurized water reactor
CN105139900B (en) A kind of 24 months reload core stowages of employing erbium burnable poison
CN108470589A (en) It is a kind of can transmuting simultaneously time actinium series nucleic and long-lived fission product the fast critical reactor core of hot mixing power spectrum
CN109036592A (en) Doping fuel-involucrum combination for transmuting
CN108550405A (en) Mox fuel stick, mox fuel component and the method for flattening axial power
Bethe The fusion hybrid
Dwiddar et al. Investigation of different scenarios of thorium–uranium fuel distribution in the VVER-1200 first core
CN104952492B (en) Carry gadolinia fuel rod and with the fuel assembly and pressurized water reactor core for carrying gadolinia fuel rod
CN111627569B (en) Transuranic fuel, preparation method thereof and transmutation method
CN103366852B (en) A kind of high throughput thermally neutron pile reactor core for transmuting
Rineiski et al. Sodium void effect reduction and minor actinide incineration in ESFR
Peng et al. Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor
CN208173248U (en) It is a kind of can transmuting simultaneously time actinium series nucleic and long-lived fission product the fast critical reactor core of hot mixing power spectrum
Wilson et al. Economy of uranium resources in a three-component reactor fleet with mixed thorium/uranium fuel cycles
CN105280256A (en) Leading fuel assembly mixing reactor core loading method
Syarifah et al. The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor
Su'ud Conceptual core analysis of long life PWR utilizing thorium-uranium fuel cycle
Chen et al. Transmutation of Minor Actinides and Power Flattening in PWR MOX Fuel
KR101488555B1 (en) Fuel for heavy-water reactor or graphite reactor and process for producing the same
Ramdhani et al. Neutronics Analysis of SMART Small Modular Reactor using SRAC 2006 Code
Trianti et al. Neutronic Performance of Small Long-Life Boiling Water Reactor Using Thorium as Fuel and the Addition of Protactinium as Burnable Poisons
Galahom et al. Design boiling water reactor core model using MCNPX for studying the burnable poisons and the axial enrichment fuel effect on the neutronic characteristics
Bánáti et al. Development of a Coupled PARCS/RELAP5 Model of the Ringhals-3 PWR
Raitses et al. Non-proliferative, thorium-based, core and fuel cycle for pressurized water reactors

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant