CN109147965A - A kind of more single sheet free modular slightly enriched uranium uranium foil target parts - Google Patents

A kind of more single sheet free modular slightly enriched uranium uranium foil target parts Download PDF

Info

Publication number
CN109147965A
CN109147965A CN201810951106.8A CN201810951106A CN109147965A CN 109147965 A CN109147965 A CN 109147965A CN 201810951106 A CN201810951106 A CN 201810951106A CN 109147965 A CN109147965 A CN 109147965A
Authority
CN
China
Prior art keywords
uranium
target
foil
slightly enriched
enriched uranium
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.)
Pending
Application number
CN201810951106.8A
Other languages
Chinese (zh)
Inventor
于宁文
罗志福
邓新荣
沈亦佳
向学琴
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.)
China Institute of Atomic of Energy
Original Assignee
China Institute of Atomic of Energy
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 China Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN201810951106.8A priority Critical patent/CN109147965A/en
Publication of CN109147965A publication Critical patent/CN109147965A/en
Pending legal-status Critical Current

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
    • G21C3/02Fuel elements
    • G21C3/28Fuel elements with fissile or breeder material in solid form within a non-active casing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/07Casings; Jackets characterised by their material, e.g. alloys
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Metallurgy (AREA)
  • Particle Accelerators (AREA)

Abstract

The invention belongs to radioactive substance preparation technical fields, are related to a kind of more single sheet free modular slightly enriched uranium uranium foil target parts.The slightly enriched uranium uranium foil target part is for irradiating production fission99Mo, including target cylinder, slightly enriched uranium uranium foil, target core plug, tamponade, sealing cover, the interior slightly enriched uranium uranium foil that multi-disc is freely combined by being put into the target core plug of the hollow target cylinder are pressed between the inner wall and the target core plug of the target cylinder;In the target cylinder, the top of the target core plug compresses the target core plug for the tamponade;The both ends of the target cylinder are by the sealing cover sealing.More single sheet free modular slightly enriched uranium uranium foil target parts of the invention can preparation process simplify, improve irradiation efficiency, reduce self-shileding, the safety during reactor irradiation, subsequent solution target is simple and guarantees production99Mo mass.

Description

A kind of more single sheet free modular slightly enriched uranium uranium foil target parts
Technical field
The invention belongs to radioactive substance preparation technical fields, are related to a kind of more single sheet free modular slightly enriched uranium uranium foils Target piece.
Background technique
99mTc is most widely used radiodiagnosis nucleic in modern nuclear medicine, which is usually by artificial radioactivity Nucleic99Mo decays to obtain, half-life period 66h.Production99The main approach of Mo is reactor irradiation235It is raw by fission reaction after U At99Mo and other products, wherein99Mo accounts for 6.1% (mass percent) of fission product.Uranium target (235U) enter after heap in thermal neutron Under the action of fission reaction, reaction cross-section 586b can occur.Fission reaction equation are as follows:
235U+n→236U+99Mo+134Sn+3n
Using high-enriched uranium (HEU,23590% or more U mass percentage content) large-scale production fission99Mo is complete at present Ball99The main source of Mo.But HEU is material for nuclear weapons, uses and is limited by Treaty on Non-Proliferation of Nuclear Weapons (NPT).Therefore, international International Atomic Energy Agency and American Positive are pushed using slightly enriched uranium (LEU) production fission99The technology of Mo becomes global fission99Mo The major way of production.
It prevents nuclear proliferation in slightly enriched uranium235The mass percentage content of U is limited to 20% hereinafter, up to 19.75%.Institute It is fissioned with slightly enriched uranium target piece and the production of high-enriched uranium target piece99The main distinction of Mo is: if production same amount99Mo, slightly enriched uranium target The content of uranium is 5-6 times of high-enriched uranium target piece in part;In slightly enriched uranium target piece fission product239Pu content increases 20-30 times.At present The high-enriched uranium target piece used in the world substantially uses aluminum jacket target piece, if the system in the form of high-enriched uranium target piece dispersoid or alloy Make slightly enriched uranium target piece, then target piece volume increases very much, causes to be stranded greatly very much to in-pile irradiation, target piece transport and target solution target technique processed Difficulty, to guarantee99The yield and purity of Mo brings very big challenge.
Therefore, it is necessary to design a kind of slightly enriched uranium uranium foil target part, with can preparation process simplify, improve irradiation efficiency, reduce Self-shileding, the safety during reactor irradiation, subsequent solution target is simple and guarantees production99Mo mass.
Summary of the invention
The object of the present invention is to provide a kind of more single sheet free modular slightly enriched uranium uranium foil target parts, with being capable of preparation process Simplify, improve irradiation efficiency, reduce self-shileding, the safety during reactor irradiation, subsequent solution target is simple and guarantees production99Mo Quality.
The problems such as such slightly enriched uranium uranium foil target part will consider thickness, quality, size and the thermal stress of uranium foil when designing, also Consider reactor heat transfer condition, and during reactor irradiation the problems such as uranium foil fission recoil protective layer.It is hard due to uranium Degree and ductility cause the difficulty of rolling, so being badly in need of a kind of easily prepared and can satisfy heap according to the uranium foil target part needed.
In order to achieve this, it is low dense that the present invention provides a kind of more single sheet free modulars in the embodiment on basis Uranium uranium foil target part, the slightly enriched uranium uranium foil target part is for irradiating production fission99Mo, including target cylinder, slightly enriched uranium uranium foil, target core Plug, tamponade, sealing cover,
The slightly enriched uranium uranium that multi-disc is freely combined by being put into the target core plug in the hollow target cylinder Foil is pressed between the inner wall and the target core plug of the target cylinder;
In the target cylinder, the top of the target core plug compresses the target core plug for the tamponade;
The both ends of the target cylinder are by the sealing cover sealing.
The principle of the present invention is as follows.
1, slightly enriched uranium uranium foil target part
(1) using the geometric dimension of smaller and appropriate slightly enriched uranium uranium foil target part, the heat generated in irradiation is discharged in time Amount guarantees irradiation safety
Uranium can release very high energy in fission process, and the mass number of different fission products is generated during uranium fission 95-139, ten thousand electron-volts of the about 190-200 that accordingly gives off energy (1,000,000 electron-volts be converted into heat be equivalent to 3.83 × 1017Kilocalorie).The energy that 1 kilogram of uranium nuclear fuel is released in complete fission can be estimated are as follows:
2.563×1021×190×3.83×1017Kilocalorie=18.7 × 109Kilocalorie
18.7×109/ 860=21.7 × 106Kilowatt/hour
About 15%235Change isotope after the atom capture neutron of U236U, it is practical to release without participating in fission process Energy: 0.85 × 18.7 × 109=16 × 109Kilocalorie
0.85×18.7×109/ 860=18.4 × 106Kilowatt/hour
Therefore, the geometric dimension of the smaller and appropriate slightly enriched uranium uranium foil target part of use, production when can timely irradiate target piece Raw heat releases, to guarantee irradiation safety.
Consider the safety of target piece involucrum, it is desirable that not more than 300 DEG C of the surface temperature of uranium.
Calculate volume heat release rate of the uranium at 300 DEG C:
qm=GfNffσfΦ
In formula:
NffFor fissionable fuel density,
Av is Avgadro constant 6.023 × 1023
MffFor the molecular mass of fissionable fuel used235U;
R is enrichment, and fissionable fuel and total fuel mass are than 0.1975;
ρfmThe density for being uranium at 300 DEG C, is 18.87g/cm3
F is u empirical correction factor, f (T)=f (400 DEG C)=0.75;
σf0For fission fuel neutron absorption cross-section 577.1b=577.1 × 10-24cm2
I is atomicity possessed by each fuel molecule,235U is 1;
σfNeutron absorption cross-section is corrected at 300 DEG C for fission fuel;
σf=0.8862f (300 DEG C) σf0(T0/T)0.5=253.2b=253.2 × 10-24cm2
Φ is neutron fluence rate, is 6 × 1014n·cm-2·s-1
GfIt is 190MeV for fuel fission average energy.
It is assumed that neutron fluence rate Φ is 6 × 1014n·cm-2·s-1,
The then volume heat release rate of uranium:
qm=2.07 × 1017MeV/s.cm3=2.07 × 1017×3600×4.44×10-17=32788.8w/cm3= 32.8kw/cm3
As shown in Figure 1, uranium foil thickness b is 120 μm, 60 μm of center to edge, heat transfer type mainly presses Fourier's law matter Measure uniform platen surface heat transfer.The heat that instantaneously transmits of the hot-fluid from uranium foil center to edge in dt is Q, and direction of heat flow length is Dn, the heat that uranium foil platen surface is conducted in the unit time:
In formula:
DQ is heat conduction rate, w;
A is uranium foil heat-conducting area, m2
Dt/dn is temperature gradient, K/m;
Q is center heat, w;
λ is uranium foil thermal coefficient, w/m.K;
R is thermal conduction resistance, K/w.
As shown in Fig. 2, uranium foil fission recoil only 10 μm of protective layer nickel plating thickness, thermal resistance resistance is very small, can timely by The heat on uranium foil surface transfers out.
As shown in figure 3, monolithic uranium foil area is approximately plane relative to aluminium target tube inner surface because uranium foil area is smaller, It is three layers of planomural heat transfer from uranium foil center to aluminium target drum outer wall conduction heat.
Three layers of the temperature difference: Δ t1=t1-t2Δt2=t2-t3Δt3=t3-t4
In formula:
b1For uranium foil center to edge thickness, m;
b2For nickel layer thickness, m;
b3For aluminium target barrel thickness, m;
λ1For uranium foil thermal coefficient, 27.6w/m.K;
λ2For nickel thermal coefficient, 57w/m.K;
λ3For aluminium thermal coefficient, 228w/m.K;
A be monolithic uranium foil heat-conducting area, 4.41 × 10-3m2
Monolithic slightly enriched uranium foil weight only 1.008g, nuclear reaction thermal energy is smaller, and 120 μm of the thickness area that compares is much smaller, Nuclear reaction thermal energy can be exported rapidly.
Therefore, the slightly enriched uranium foil for designing smaller geometric dimension is conducive to quick target piece and releases very high heat.
(2) uranium foil has relatively thin thickness to be conducive to the heat derives in time generating uranium foil, ensures irradiation safety
Consider the volume heat release of slightly enriched uranium when irradiation, reduce self-shileding improve irradiation efficiency, target piece enter heap irradiation technique and Pure slightly enriched uranium, is made the uranium foil shape of relatively thin and appropriate geometric dimension by target piece processing and the problems such as purifying process after subsequent irradiation Formula.
The thickness of uranium foil reduces self-shileding to irradiation efficiency is improved, and improves fission99Mo yield is most important.In certain uranium Under conditions of amount, relatively thin uranium foil can increase the irradiated area of uranium foil, and the burnup for improving uranium obtains more99The yield of Mo. Uranium foil can generate very high heat in irradiation process, but the thermal capacitance value of uranium can be increased with the raising of temperature, different temperatures Under thermal capacitance value, following calculation formula can be used:
CP=3.15+8.44 × 1a13T+0.8×105T2
The energy released in fission process with uranium, uranium can generate very high heat, and the temperature of uranium core can rise very It is high.For the heat of uranium core in fission sheds in time, prevent uranium core temperature excessively high, it is therefore desirable to which uranium foil has relatively thin thickness to have Conducive to the heat derives in time generating uranium foil, irradiation safety is ensured.
(3) uranium foil face square _type layout guarantee uniform heat release in linear expansion and volume expansion is also conducive to maintain target piece Configuration in irradiation
During uranium fission, since the kinetic energy of lattice absorption fission product generates fission fragment, fission fragment is some bands The heavy particle of electricity, the lattice that can impact uranium generate localized hyperthermia, referred to as " thermal spike " phenomenon.Uranium is in irradiation process, in " heat Under the action of peak ", uranium core temperature, which increases, occurs Phase shift, causes the volume expansion of uranium that creep occurs, uranium surface is made to wrinkle Folding generates orange peel effect, and the longitudinally varying length of uranium can be increased and keep wall thickness thinning in irradiation process.In order to guarantee uranium Foil keeps best stability under the influence of different condition during reactor irradiation, it is therefore desirable to calculate the heated rear line of uranium foil Property expansion and volume expansion with verify design.
Creep occurs for uranium volume easily dilatancy after heated, especially deforms most when temperature rises to 100-300 DEG C It is obvious.Creep reaches maximum value at 200 DEG C, is reduced to the zero stopping deformation of creep to 400 DEG C of coefficients of growth.
At different temperatures, the average value of linear expansion and the coefficient of cubical expansion generally can be according to following empirical formula for uranium It is calculated:
To [100] direction
LT=L25×(1+10.64×10-6T+47.46×10-9T2-16.65×10-12T3)
To [010] direction
LT=L25×(1-1.503×10-6T+9.09×10-9T2-31.79×10-12T3)
To [001] direction
LT=L25×(1+19.69×10-6T-7.79×10-9T2+43.26×10-12T3)
Wherein, LTLength when being T DEG C, L25Length when being 25 DEG C, T are temperature.
Table 1: the variation of monolithic slightly enriched uranium foil geometric dimension at 400 DEG C of irradiation temperature
" thermal spike " estimation
Fission fragment.
Uranium foil is in 400 DEG C of irradiation temperature hereinafter, for uranium foil under the action of with fission gas, deformation is minimum in fission process.
As a result it can determine, the slightly enriched uranium foil of design geometrical variations in irradiation are minimum, not will receive irradiation substantially It influences;Monolithic uranium foil heat small in size that can give out generation in time in irradiation process, keeps the stabilization of geometric dimension.
(4) multi-disc uranium foil independent assortment is to meet the needs of different yields
It is considered as reactor irradiation, each neutron flux is different, according to99Mo yield needs the different slightly enriched uraniums of corresponding target piece Loading amount, designs and produces the uranium foil of the geometric dimension of appropriate form, and the loading amount of different uranium foils can be used to guarantee in target piece99The production of Mo Amount:
In formula:
A is99Mo yield, Bq;
N0It is a for the atomicity of target nucleus;
M is235The molal weight of U;
Φ is neutron flux, ncm-2·s-1
σfFor235U fission cross section, cm-2
Y is99Mo fission yield is 6.13%;
λ is99Mo decay coefficient, s-1
AvFor Avgadro constant:
t1For target piece irradiation time, s-1
t2Post-processing and purifying process time, s are irradiated for target piece-1
The radiation parameter for considering differential responses heap, prepares the slightly enriched uranium foil of appropriate size, can flexibly assemble single target piece Slightly enriched uranium amount.
2, target piece support component is combined
(1) target cylinder
According to the requirement of reactor original part heat release and cutting solution target, design target piece is aluminum jacket cylinder target piece.Aluminium is preferable Reactor heat release original part shell material, 650 DEG C of fusing point, linear expansion coefficient 2.36 × 10-5/ DEG C, thermal conductivity 237W/m.k, Hardness HB95.Compared with zirconium Zr, the fusing point and linear expansion coefficient of aluminium are relatively worse than zirconium, but thermal conductivity is better than zirconium Zr.It is appropriate hard Degree can provide required strength and stiffness for uranium foil, it is particularly advantageous to which subsequent solution target works.The gold bigger than aluminium hardness Belong to as zirconium also may be selected as target cylinder material.
(2) target core plug and tamponade
According to the requirement of target piece heat release, it is put into aluminum target core plug in target cylinder by uranium foil and target cylinder inner wall jam-packed, is made into heap Spoke method.Target core plug top is pressed into aluminum tamponade, and uranium foil is made to be connected in axial direction with aluminum jacket, sealing aluminium lid above and below target cylinder.
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein the target cylinder is the target cylinder of aluminum, with a thickness of 1-4mm.
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein the mass percentage content of uranium is 2-19.75% in slightly enriched uranium uranium foil described in every.
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein slightly enriched uranium uranium foil described in every is square, side length 20-30mm, with a thickness of 100-150 μm, density 18.1- 19.1g/cm3
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein slightly enriched uranium uranium foil described in every is square, side length 21mm, with a thickness of 120 μm, density 19.05g/cm3
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein slightly enriched uranium uranium foil described in every has 7-20 μm of package nickel coating.
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein slightly enriched uranium uranium foil described in multi-disc is arranged in mosaic structure on the inner wall of the target cylinder.
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein being 1-28 piece along the piece number of the inner wall one week slightly enriched uranium uranium foil placed of the target cylinder.
In a preferred embodiment, the present invention provides a kind of more single sheet free modular slightly enriched uranium uranium foil targets Part, wherein target core plug, the tamponade and/or the sealing cover are aluminum.
The beneficial effects of the present invention are more single sheet free modular slightly enriched uranium uranium foil target parts of the invention can be prepared Technique simplifies, and improves irradiation efficiency, reduces self-shileding, and the safety during reactor irradiation, subsequent solution target is simple and guarantees to produce 's99Mo mass.
It is anti-in uranium foil plating nickel on surface the present invention provides a kind of slightly enriched uranium uranium foil target part convenient for preparing, solving the molten target of target Protective layer is rushed, is easily assembled to, is radiated when conducive to heap photograph, has been reached in heap according to production fission99Irradiation efficiency is high when Mo, irradiates safety Property good and small radioactive pollution purpose.
Beneficial effects of the present invention are embodied in:
(1) the heat release in irradiation of slightly enriched uranium foil target part is fast, reduces heap according to risk, this is production99Mo lays the foundation. The present invention ensure that heat dissipation from design.Since the small heat release of monolithic uranium foil size is fast, overall heat release effect is better than monolithic after combination Large scale uranium foil can reduce heap according to risk so carrying out heap photograph using combination slightly enriched uranium uranium foil target part of the invention.
(2) slightly enriched uranium foil target part preparation process is simple, and small uranium foil is easier to roll, and reduces the wind that radioactive pollution occurs Danger (uranium is radioactive metal, and hardness is larger, and rolling is difficult and is easy to happen radioactive pollution).
(3) solution target is easy to operate, need to only take out target cylinder inner wall uranium foil, understands target efficiency to improve.Of the invention is low For dense uranium foil target part after the completion of reactor irradiation, the aluminum barrel of package is unlocked in cutting, is only taken out uranium foil and is dissolved, after then carrying out Continuous chemical treatment, this greatly reduced Spent Radioactive liquid measure, shorten the Chemical Decomposition operating time.Therefore, of the invention It is more laborsaving in solution target, it improves and understands target efficiency, be conducive to more target piece solution target operations in hot cell.
(4) target cylinder need to only be cut when the operation of solution target and takes out uranium foil, it reduce the risks that radioactive pollution occurs.This hair Bright solution target need to only cut target cylinder end face when operating, and do not have the risk for cutting to uranium foil, can keep the original shape of uranium foil in this way State, the small dissolution for being conducive to complete uranium foil of uranium foil size;Simultaneously can also protection staff safe operation, protection environment avoid pollution.
Detailed description of the invention
Fig. 1 is uranium foil heat conductive relationship schematic diagram.
Fig. 2 is uranium foil nickel coating heat conductive relationship schematic diagram.
Fig. 3 is uranium foil target part heat conductive relationship schematic diagram.
Fig. 4 is illustrative more single sheet free modular slightly enriched uranium uranium foil target parts of the invention in specific embodiment External structure (being free of target core plug, tamponade, sealing cover) schematic diagram.
Fig. 5 is illustrative more single sheet free modular slightly enriched uranium uranium foil target parts of the invention in specific embodiment Axial sectional view.
Specific embodiment
For temperature in the reactor of 100 DEG C or so water coolings, aluminium is most widely used heat release original part sheathing material, is selected The stronger 6061LT6 state aluminum pipe of hardness is as heat release original part sheathing material.Reactor irradiation channel diameter substantially in 70-80mm, Following illustrative sheets are designed according to irradiation channel internal irradiation suspender and the out technique of heap gripping apparatus and the requirement of reactor original part heat release More single sheet free modular slightly enriched uranium uranium foil target parts of invention.
The structure of illustrative more single sheet free modular slightly enriched uranium uranium foil target parts of the invention is as shown in Figs. 1-2, packet Include target cylinder 1, target core plug 2, slightly enriched uranium uranium foil 3, tamponade 4, sealing cover 5.
The target cylinder 1 of hollow aluminum (outer diameter 56mm, thick 2mm, high 100mm place the 3 high 85.44mm of section of slightly enriched uranium uranium foil) The slightly enriched uranium uranium foil 3 that multi-disc is freely combined in the interior target core plug 2 by being put into aluminum is pressed in the inner wall and target core plug of target cylinder 1 Between 2.
The mass percentage content of uranium is 19.75% in every slightly enriched uranium uranium foil 3, and shape is square, and side length is 21mm, with a thickness of 120 μm, density 19.05g/cm3.Every slightly enriched uranium uranium foil 3 has 10 μm of package nickel coating.28 low Dense uranium uranium foil 3 is arranged in 4 layers of mosaic structure on the inner wall of target cylinder 1, along one week (inner wall week of target cylinder 1 of inner wall of target cylinder 1 A length of 163.28mm) one layer place 7 slightly enriched uranium uranium foils 3.The center of circle of the inner wall at the both ends and target cylinder 1 of every slightly enriched uranium uranium foil 3 The angle of formation is 48 °, i.e., the radian of every slightly enriched uranium uranium foil 3 is 4/15 π.Under the above structure and size condition, every low The heat transfer type of dense uranium uranium foil 3 is mainly the platen surface heat transfer for pressing Fourier's law uniform quality.At this point, hot-fluid is by slightly enriched uranium uranium 3 center of foil is Q in the heat of dt instantaneously transmitted, direction of heat flow length is dn, slightly enriched uranium uranium foil 3 in the unit time to edge The heat of platen surface conduction meets calculated result.
In target cylinder 1, the top of target core plug 2 compresses target core plug 2 for the tamponade 4 of aluminum.
The both ends of target cylinder 1 are by 5 sealing of sealing cover of aluminum.
More single sheet free modular slightly enriched uranium uranium foil target parts of the invention of above-mentioned example are completed in reactor irradiation Afterwards, the target cylinder 1 of package is unlocked in cutting, is only taken out slightly enriched uranium uranium foil 3 and is dissolved, then carries out subsequent chemistry processing.This Sample greatly reduced Spent Radioactive liquid measure, shorten the Chemical Decomposition operating time.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art Mind and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention Within enclosing, then the present invention is also intended to include these modifications and variations.Above-described embodiment or embodiment are only to the present invention For example, the present invention can also be implemented with other ad hoc fashions or other particular form, without departing from of the invention Main idea or substantive characteristics.Therefore, the embodiment of description is regarded as illustrative and non-limiting in any way.This The range of invention should be illustrated that any variation equivalent with the intention and range of claim also should include by appended claims Within the scope of the invention.

Claims (9)

1. a kind of more single sheet free modular slightly enriched uranium uranium foil target parts, it is characterised in that: the slightly enriched uranium uranium foil target part is used In irradiation production fission99Mo, including target cylinder, slightly enriched uranium uranium foil, target core plug, tamponade, sealing cover,
The slightly enriched uranium uranium foil quilt that multi-disc is freely combined by being put into the target core plug in the hollow target cylinder It is pressed between the inner wall and the target core plug of the target cylinder;
In the target cylinder, the top of the target core plug compresses the target core plug for the tamponade;
The both ends of the target cylinder are by the sealing cover sealing.
2. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: the target cylinder is the target cylinder of aluminum, With a thickness of 1-4mm.
3. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: uranium in slightly enriched uranium uranium foil described in every Mass percentage content is 2-19.75%.
4. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: slightly enriched uranium uranium foil described in every is pros Shape, side length 20-30mm, with a thickness of 100-150 μm, density 18.1-19.1g/cm3
5. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: slightly enriched uranium uranium foil described in every is pros Shape, side length 21mm, with a thickness of 120 μm, density 19.05g/cm3
6. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: slightly enriched uranium uranium foil described in every has 7- 20 μm of package nickel coating.
7. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: slightly enriched uranium uranium foil is described described in multi-disc Target cylinder inner wall on be arranged in mosaic structure.
8. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: put along inner wall one week of the target cylinder The piece number for the slightly enriched uranium uranium foil set is 1-28 piece.
9. slightly enriched uranium uranium foil target part according to claim 1, it is characterised in that: the target core plug, the tamponade and/ Or the sealing cover is aluminum.
CN201810951106.8A 2018-08-20 2018-08-20 A kind of more single sheet free modular slightly enriched uranium uranium foil target parts Pending CN109147965A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201810951106.8A CN109147965A (en) 2018-08-20 2018-08-20 A kind of more single sheet free modular slightly enriched uranium uranium foil target parts

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201810951106.8A CN109147965A (en) 2018-08-20 2018-08-20 A kind of more single sheet free modular slightly enriched uranium uranium foil target parts

Publications (1)

Publication Number Publication Date
CN109147965A true CN109147965A (en) 2019-01-04

Family

ID=64790295

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201810951106.8A Pending CN109147965A (en) 2018-08-20 2018-08-20 A kind of more single sheet free modular slightly enriched uranium uranium foil target parts

Country Status (1)

Country Link
CN (1) CN109147965A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3985686A1 (en) * 2020-10-14 2022-04-20 Narodowe Centrum Badan Jadrowych Method of preparation of the uranium target for the production of molybdenum, molybdenum production process and the uranium target for the production of molybdenum

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6160862A (en) * 1993-10-01 2000-12-12 The United States Of America As Represented By The United States Department Of Energy Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium
US7100670B1 (en) * 2003-09-12 2006-09-05 The United States Of America As Represented By The United States Department Of Energy Method for fabricating uranium foils and uranium alloy foils
US20100282375A1 (en) * 2009-05-06 2010-11-11 Babcock & Wilcox Technical Services Y-12, Llc Method of Fabricating a Uranium-Bearing Foil
CN103038831A (en) * 2010-07-29 2013-04-10 由俄勒冈州高等教育管理委员会代表的俄勒冈州立大学 Isotope production target
CN203366770U (en) * 2013-07-25 2013-12-25 中国原子能科学研究院 Multistage fission target chamber system
CN106875999A (en) * 2017-01-03 2017-06-20 中国原子能科学研究院 One kind is for irradiating production fission99The slightly enriched uranium uranium foil target part of Mo

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6160862A (en) * 1993-10-01 2000-12-12 The United States Of America As Represented By The United States Department Of Energy Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium
US7100670B1 (en) * 2003-09-12 2006-09-05 The United States Of America As Represented By The United States Department Of Energy Method for fabricating uranium foils and uranium alloy foils
US20100282375A1 (en) * 2009-05-06 2010-11-11 Babcock & Wilcox Technical Services Y-12, Llc Method of Fabricating a Uranium-Bearing Foil
CN103038831A (en) * 2010-07-29 2013-04-10 由俄勒冈州高等教育管理委员会代表的俄勒冈州立大学 Isotope production target
CN203366770U (en) * 2013-07-25 2013-12-25 中国原子能科学研究院 Multistage fission target chamber system
CN106875999A (en) * 2017-01-03 2017-06-20 中国原子能科学研究院 One kind is for irradiating production fission99The slightly enriched uranium uranium foil target part of Mo

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3985686A1 (en) * 2020-10-14 2022-04-20 Narodowe Centrum Badan Jadrowych Method of preparation of the uranium target for the production of molybdenum, molybdenum production process and the uranium target for the production of molybdenum
WO2022079600A1 (en) * 2020-10-14 2022-04-21 Narodowe Centrum Badan Jadrowych A method of fabricating a uranium target for producing molybdenum, a process of producing molybdenum, and a uranium target for producing molybdenum

Similar Documents

Publication Publication Date Title
US20090274258A1 (en) Compound isotope target assembly for production of medical and commercial isotopes by means of spectrum shaping alloys
AU2021380945B2 (en) Breeder blanket
CN109147965A (en) A kind of more single sheet free modular slightly enriched uranium uranium foil target parts
Wohlmuther et al. The spallation target of the ultra-cold neutron source UCN at PSI
Shmelev et al. Use of molybdenum as a structural material of fuel elements for improving the safety of nuclear reactors
Kim et al. Synthesis and characteristics of ternary Be–Ti–V beryllide pebbles as advanced neutron multipliers
Zhou et al. Deuterium retention in molten salt electrodeposition tungsten coatings
Choudhury et al. Converter target chemistry–A new challenge to radioanalytical chemistry
Sukegawa et al. Flexible heat-resistant neutron and gamma-ray shielding resins
RU142204U1 (en) TARGET FOR PROTON ISOTOPE GENERATION
Lu et al. Neutronics Analysis of Helium Cooled Ceramic Breeder Blanket with S-shaped Lithium Zone and Cooling Plate for CFETR
Sounalet et al. Strontium-82 and future Germanium-68 production at the ARRONAX facility
Vatulin et al. Alternative versions of inert matrix fuel for the use of civil and weapons-grade plutonium in reactors
CN108039218A (en) A kind of device using commercial presurized water reactor irradiation production Pu-238
Konishi et al. < Advanced Energy Generation Division> Advanced Atomic Energy Research Section
Sekimoto et al. Conceptual design of the blanket and superheater in compact fusion advanced Rankine cycle
Landini et al. Evaluation of microwave technology in the additional purification of Mo-99, produced from LEU targets
Chemerisov Development of Thermionic Energy Converter for Radioisotope Batteries (Final CRADA Report)
Udup et al. Preliminary results of SPIRAL-2 thermo mechanical neutron converter characteristics
CN104934091B (en) selectively passing material and preparation method thereof
Alsmiller Jr et al. Development of zinc oxide-multi-walled carbon nanotube hybrid nanofluid for energy-efficient heat transfer application: A thermal lens study
Higatsberger 36. Fuel Irradiation Capsule
Wei et al. Irradiation of the fission isotope target tube in SPRR-300
Protopopov et al. The mass distribution of fragments resulting from the fission of 235U, 238U and 238Pu induced by 14· 6 MeV neutrons
Spitsyn et al. Production of weighable amounts of 99Tc by neutron irradiation of molybdenum

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
RJ01 Rejection of invention patent application after publication
RJ01 Rejection of invention patent application after publication

Application publication date: 20190104