CN101866701A - New method for preparing radionuclide 98Tc - Google Patents
New method for preparing radionuclide 98Tc Download PDFInfo
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- CN101866701A CN101866701A CN 201010174356 CN201010174356A CN101866701A CN 101866701 A CN101866701 A CN 101866701A CN 201010174356 CN201010174356 CN 201010174356 CN 201010174356 A CN201010174356 A CN 201010174356A CN 101866701 A CN101866701 A CN 101866701A
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Abstract
The invention discloses a new method for preparing radionuclide 98Tc, which is mainly technically characterized by comprising the following steps of: dissolving a Mo target irradiated by deuteron (2H) by using H2O2 sold on the market, converting the dissolved Mo and Tc into Na2MoO4 and Na2TcO4 by using NaOH, and maintaining the basicity of the solution at about 10 percent; and in the process of separating the MO from the 98Tc, putting the Na2MoO4 solution containing 98Tc on a Dowex-1 anion exchange resin column, eluting the Mo from the Dowex-1 anion exchange resin column by using 9.5 to 10.5 weight percent NaOH, eluting other impurities by using 1.5 to 2.5 mol/L HCL and 2 to 3 mol/L HNO3 respectively, and finally eluting the Dowex-1 anion exchange resin column by using 7.0 to 8.0 mol/L HNO3 in a volume which is 5.0 to 8.0 times that of the exchange column to obtain high-purity Na2TcO4 solution containing the 98Tc. In the 98Tc prepared by the invention, the atomic ratio of the Mo to the Tc is less than 1 percent, and the radioactive nucleus purity of the Tc is over 99.9 percent; and the preparation method has the advantages of simple operational procedure and high safety.
Description
Technical field
The present invention relates to the isotope technology field, more specifically, relate to a kind of by d nuclear (
2H) irradiation
98The Mo target is produced radioactive nuclide
98The method of Tc.
Background technology
98Tc is the longest a kind of nucleic of half life period in the isotope of Tc, reaches 4.2 * 10
6A.
98Tc does not exist at occurring in nature, only could produce in class nuclear activities such as nuclear explosion.Therefore,
98Tc can be used for the having a nuclear test analysis again of data also can be used for the geochemistry and the researching nuclein migration of technetium.
98Tc generally produces by accelerator.Produce with accelerator
98Tc, the method for prior art mainly adopt proton (
1H) and helion (
3He) bombardment metal M o.Bibliographical information is arranged with the 22MeV proton (
1H) bombardment Mo target obtains about 10 μ g's
98Tc, and the isotopic abundance that has provided Tc form (
95Tc :～0.5%,
97Tc:56.0%,
98Tc:17.3%,
99But do not have concrete experimentation Tc:26.7%).Other bibliographical information is arranged with the 23MeV helion (
3He) and the 19MeV helion (
3He) bombardment Mo target has only been studied the excitation energy that helion bombards the Mo target.
Produce with accelerator
98Tc relates to the preparation of Mo target, the irradiation of Mo target, the dissolving and the technology such as Mo separates with the radiochemistry of Tc of irradiation Mo target.The wherein preparation of Mo target adopts that generally electrochemical plating, vacuum sputtering, Mo sheet mounting method, Mo plate are directly processed etc.The dissolving of irradiation Mo target mainly contains aqua regia dissolution method, red fuming nitric acid (RFNA) or the concentrated sulphuric acid, 10% NaOH (or 1mol/L NaOH) and 30%H
2O
2Solution heating for dissolving method, ammoniacal liquor and 30%H
2O
2Mixed solution dissolution method etc.The concentrated acid dissolution method is operated more loaded down with trivial details owing to need to add a large amount of alkali neutralizing acids; Ammoniacal liquor and 30%H
2O
2The mixed solution dissolution method because dissolving back alkalescence is on the low side, need adds alkali and make solution become strong basicity, operates also more loaded down with trivial details.10% NaOH (or 1mol/LNaOH) and 30%H
2O
2Solution heating for dissolving method, course of dissolution not only need heating, and dissolution velocity is fast inadequately, effect is also general.The radiochemistry separation method of Mo is many, and Al is arranged
2O
3Chromatography, anion exchange resins exchange process, Fe (OH)
3Coprecipitation, solvent extraction or several method are used in combination etc.To from a few gram Mo, isolate trace (～μ g level)
98Tc, it is very difficult adopting conventional method, does not also reach the requirement of separation and purification.Co-precipitation and solvent extraction complex operation, the recovery of Tc is not high; Al
2O
3The chromatography operation is also more loaded down with trivial details, Al
2O
3Also difficulty of processing, and cause that easily the leakage of Mo is worn etc.There is bibliographical information to pass through reactor
98Mo (n, γ)
99Tc reacts production
99Tc produces in its reaction
99In the process of Tc, adopt cation exchange column and anion-exchange column to combine to carry out separating of Mo and Tc, Co, Ag, this separation method is earlier with ammoniacal liquor and 30%H
2O
2Mixed solution dissolving irradiation Mo target, excessive H is removed in water-bath
2O
2, at first go up the Hydrogen cation exchange column after sample is water-soluble, use water wash; Leacheate is gone up anion-exchange column again, washes with water earlier, with potassium oxalate-KOH solution Mo drip washing is got off then, and ammonium thiocyanate drip washing Tc is adopted in washing at last again.This method has been used ion exchange column twice, operates more loaded down with trivial detailsly, and has adopted ammonium thiocyanate drip washing Tc, and elution volume is big (about 400-500mL) also, and there is certain danger in need with the ammonium thiocyanate heating and decomposition in last solution; In last result, do not provide related data (atomic ratio that comprises Mo/Tc) yet.
Summary of the invention
Produce radioactive nuclide at prior art
98The present situation of Tc, purpose of the present invention aim to provide a kind of d nuclear (
2H) irradiation bombardment Mo target produce the Tc/Mo atomic ratio less than 1%, radionuclide purity is greater than 99.9%
98Tc (contains
95Tc,
97Tc and
99The isotope of Tc such as Tc) new method, problems such as complex operation, the leacheate volume that overcomes prior art separation Mo, Tc existence simultaneously is big, poor stability.
The radioactive nuclide of producing provided by the invention
98The method of Tc mainly may further comprise the steps:
(1) Mo target preparation: with the dimensioned Mo target sheet of Mo plate according to the accelerator target holder;
(2) Mo target irradiation: employing d nuclear (
2H) irradiation bombardment Mo target is placed behind the irradiation and is no less than 270 days and enters dissolution process;
(3) irradiation Mo target dissolving: use commercially available H
2O
2Dissolving irradiation Mo target, H
2O
2Consumption by 2.5～5.0mL/gMo, fully the dissolving back adds the NaOH of weight concentration 9.5～10.5%, converts Mo, Tc after the dissolving to Na
2MoO
4And Na
2TcO
4, the consumption of NaOH is by 5.0～8.0mL/gMo, and the basicity of solution maintains 9.5～10.5%;
(4) Mo with
98Tc separates: Dowex-1 anion-exchange resin column on the irradiation Mo target solution is zero with NaOH drip washing to the Mo detection limit in the leacheate of weight concentration 9.5～10.5%, with distilled water drip washing removal NaOH; Be the HCl drip washing of 1.5～2.5mol/L with 10.0～12.5 times of exchange column volumes, concentration respectively afterwards, 8.0～10.0 times of exchange column volumes, concentration are the HNO of 2～3mol/L
3Drip washing; The HNO that is 7.0～8.0mol/L with 5.0～8.0 times of concentration of exchange column volume at last
3Drip washing is contained
98The Na of Tc
2TcO
4Solution.
On the basis of such scheme, can further take following technical measures: will contain
98The Na of Tc
2TcO
4The solution heating evaporation is removed HNO
3, remove remaining HNO with HCl more afterwards
3, add dissolved in distilled water at last, obtain the higher Na of purity
2TcO
4Solution.
With d nuclear (
2H) irradiation Mo target preparation
98Tc can adopt enrichment
98The Mo target also can adopt natural Mo target, but because enrichment
98The Mo target is very expensive, for
98The development and production cost of Tc is too high.Given this, the present invention adopts natural Mo target preparation
98Tc.Natural Mo target mainly contains
94Mo,
95Mo,
96Mo,
97Mo,
98Mo,
99Mo and
100Isotopes such as Mo also contain elements such as micro Mg, Mn, Cr, Fe, Si in addition, with d nuclear (
2H) the natural Mo target of irradiation mainly take place (d, 2n), (d n) waits nuclear reaction, and the Tc coordination have the long half-lift of generation main:
95Tc (T
1/2=61d), by
95Mo (d, 2n)
95Tc,
94Mo (d, n)
95Tc produces;
97Tc (T
1/2=91.4d), by
97Mo (d, 2n)
97Tc,
96Mo (d, n)
97Tc produces;
98Tc (T
1/2=4.2 * 10
6A), by
98Mo (d, 2n)
98Tc,
97Mo (d, n)
98Tc produces.
Therefore, how the natural Mo target of irradiation is separated through radiochemistry and remove a large amount of Mo (gram magnitude) and non-material and trace put such as Mg, Mn, Cr, Fe, Si on a small quantity
95Zr,
95,96Nb,
94,95,97,103Radioimpurity radioactive impurities such as Ru, obtain the Tc/Mo atomic ratio less than 1% microgram magnitude, radionuclide purity is greater than 99.9%
98Tc (contains
95Tc,
97Tc and
99The isotope of Tc such as Tc), be to adopt natural Mo target preparation
98The technological difficulties of Tc.Technique scheme of the present invention has solved this technical matters well.
At the above-mentioned radioactive nuclide of producing
98In the scheme of TC, described Dowex-1 anion-exchange resin column preferably adopts the Dowex-1 anion-exchange column after handling transition.The Dowex-1 anion-exchange column was meant on the Dowex-1 resin and used distilled water, HCl, distilled water, HNO successively behind the anion-exchange resin column described transition
3, distilled water drip washing, use the NaOH drip washing of weight concentration 9.5～10.5% afterwards again, maintain 9.5～10.5% Dowex-1 anion-exchange resin column through the basicity of repeatedly drip washing process resin.In Dowex-1 anion-exchange resin column processing procedure transition, preferably use HCl, distilled water, HNO successively
3, distilled water carries out cycling elution, cycle index is no less than 3 times, it is neutral that drip washing to leacheate is.In the cycling elution process, the rate of flow in rinse of each link preferably is controlled at 0.4～0.6mL/min scope.Transition the Dowex-1 anion-exchange resin column, the Dowex-1 resin through cleaning, oven dry, grind and the screening processing, and was selected the Dowex-1 resin of particle diameter in 80～120 order scopes for use before last anion-exchange column.
At the above-mentioned radioactive nuclide of producing
98In the scheme of Tc, use commercially available H
2O
2Dissolving irradiation Mo target preferably adopts on a small quantity repeatedly dissolution mechanism, uses commercially available H at least
2O
2Dissolving irradiation Mo target 2 times, H
2O
2The each dissolving of consumption should be in 0.5～1.0mL/gMo scope, and total consumption is 2.5～5.0mL/gMo; On the irradiation Mo target solution behind the Dowex-1 anion-exchange resin column NaOH of operating weight concentration 9.5～10.5% carry out drip washing, rate of flow in rinse should be controlled at 0.4～0.6mL/min scope.
Highly purified in order to prepare
98Tc, inventor have improved the dissolving method of Mo, and in the detachment process of Mo and Tc, only adopt the Dowex-1 anion-exchange resin column, have improved the ELUTION METHOD of Mo and Tc in this course, last resulting containing
98The volume of Tc solution also reduces (60-100mL) greatly, and final separation and purification obtains
98Tc, its Mo/Tc atomic ratio is less than 1%, and radionuclide purity is greater than 99.9%.Producing
98In the prior art of Tc, known to the tool inventor, also nobody obtains the Mo/Tc atomic ratio less than 1% before the present invention finishes
98Tc, and preparation method running program of the present invention is simple, good operation safety.
Prepare highly purified
98Tc, irradiation, the dissolving of irradiation Mo target that relates to preparation, the Mo target of Mo target separates with the radiochemistry of irradiation Mo target etc.In the preparation of Mo target, consider factors such as complexity and cost, compared the quality of several method, the present invention adopts highly purified Mo plate (99.99%) directly to process irradiation Mo target.The dissolving of irradiation Mo target, the inventor finds in experimentation, uses commercially available H separately
2O
2(the about 30%H of weight concentration
2O
2) dissolving Mo is than with 10% NaOH (or 1mol/L NaOH) and commercially available H
2O
2The mixed solution dissolution velocity is fast, effective and need not heat, so the present invention has adopted the first commercially available H that uses
2O
2Dissolving Mo, Mo, Tc after back NaOH with weight concentration about 10% will dissolve convert to and separate needed Na
2MoO
4And Na
2TcO
4Pattern.The radiochemistry of irradiation Mo target is separated, in high-purity
98Be most important link in the preparation process of Tc, the inventor according to analyze, the actual conditions of simulated experiment, improved the method for drip washing Mo and drip washing Tc, only adopted the Dowex-1 anion-exchange resin column to obtain needed microgram magnitude with regard to separation and purification
98Tc, the Mo/Tc atomic ratio is less than 1%, and radionuclide purity (contains greater than 99.9%
95Tc,
97Tc and
99The isotope of Tc such as Tc).Basic skills of the present invention is after first NaOH with q.s gets off Mo drip washing, then to use HCl, HNO again
3The non-materials and a spot of of putting such as a spot of Mo that drip washing is not got off and Mg, the Mn of trace, Cr, Fe, Si
95Zr,
95,96Nb,
94,95,97,103Radioimpurity radioactive impurity drip washing such as Ru are got off, and needed
98Tc (contains
95Tc,
97Tc and
99The isotope of Tc such as Tc) still stays on the Dowex-1 anion-exchange resin column, at last with the HNO of the about 7.5mol/L of weight concentration
3Drip washing Na
2 98TcO
4Thereby, the HNO of assurance high concentration
3Do not contain other metallic ion and radioimpurity radioactive impurity in the leacheate, obtain highly purified Tc.In the radiochemistry detachment process of irradiation Mo target of the present invention, do not adopt ammonium thiocyanate drip washing Tc, improved the security of preparation high-purity Tc.
Description of drawings
Accompanying drawing 1, accompanying drawing 2 are gamma spectrums of sample.
From the gamma spectrum of accompanying drawing 1 and accompanying drawing 2 as can be seen, energy spectrum region has only
95mTc,
97The feature power spectrum of Tc does not have the power spectrum of other nucleic, illustrates to have obtained highly purified containing
98The Na of Tc
2TcO
4Solution.
Embodiment:
1.Mo the preparation of target
The highly purified Mo plate of buying (99.99%) is processed into the target sheet that meets dimensional requirement according to the requirement of accelerator target holder.Processed 4 Mo targets here altogether, 1 is used to do simulation test, and 1 is used for
99Tc
mRecovery test, other 2 are used for the irradiation target.
2.Mo the irradiation of target
Employing d nuclear (
2H) irradiation bombardment Mo target, " cooling " (are promptly placed a period of time, are no less than 270 days, so that allow short-decayed nucleic decay) after a period of time and carry out the radiochemistry separation of irradiation target.
The situation such as the table 1 of 2 Mo target sheet irradiation.
The irradiation situation of table 1Mo target
3. the separation of simulation Mo target
Because irradiation Mo target has hot, should not directly carry out the experiments such as dissolving, separation of irradiation Mo target, so need carry out earlier " cold test " before irradiation Mo target separates carrying out, promptly simulate earlier the Mo target dissolving, simulation Mo target separation and
99Tc
mRecovery test etc.
1) dissolving of simulation Mo target
Improved dissolving method is adopted in the dissolving of Mo, promptly directly uses 30%H
2O
2Dissolving Mo need not heat in the course of dissolution.
(1) dissolving of Mo sheet
The thick Mo sheet of the heavy 1-5mm of 3g is cut into small pieces (3mm * 3mm), add weight concentration 30%H 5 times by each 0.5mL/gMo score
2O
2The Mo sheet is dissolved, and course of dissolution does not need heating.Add the MoO of the NaOH of weight concentration 10% after the dissolving again with dissolving
3Convert Na to
2MoO
4, the NaOH use amount, needed whole Na before last Dowex-1 anion-exchange resin column by 8.0mL/gMo
2MoO
4The basicity of solution maintains about 10%.
(2) dissolving of simulation Mo target
To simulate Mo target sheet and be fixed in the dissolving tank, adopt the method for above-mentioned (1), add weight concentration 30%H 5 times by each 0.5mL/gMo score
2O
2Simulation Mo target sheet is dissolved, add the MoO of the NaOH of weight concentration 10% after the dissolving again dissolving
3Convert Na to
2MoO
4, the NaOH use amount is by 8.0mL/gMo, Na
2MoO
4The basicity of solution maintains about 10%, and the meltage of Mo is controlled at about 3g.
2) Mo separates
As previously mentioned, (100 ± 20 orders, φ 1.0 * 20.0cm) carry out separating of Tc and Mo etc. to adopt the Dowex-1 anion-exchange resin column.
(1) processing of Dowex-1 resin
After the cleaning of Dowex-1 resin, oven dry is ground with muller, uses the molecular sieve sub-sieve again, and it is standby to get 100 ± 20 purpose Dowex-1 resins.
With anion-exchange column on above-mentioned 100 ± 20 purpose Dowex-1 resins.Elder generation is cleaned with distilled water, uses the HCl drip washing 100-150mL of 6mol/L then, and is with distilled water that the HCl flush away is extremely neutral, uses the HNO of 3mol/L again
3Drip washing 100-150mL, with distilled water with HNO
3Flush away is to neutral.Repeat above-mentioned steps 3 times, flow speed control is at 0.5mL/min.
(2) transition of Dowex-1 resin
With 10% NaOH drip washing, the about 500mL of elution volume maintains about 10% the basicity of resin with above-mentioned treated Dowex-1 resin.
(3) separation of Mo
The Na that will contain 6g Mo
2MoO
4Solution (its basicity maintains about 10%) is gone up the Dowex-1 anion-exchange resin column after transition, uses 10% NaOH drip washing then, flow speed control about 0.5mL/min, its elution volume and content such as table 2.The content metric measurement of Mo.
Metric measurement Mo: sample thief is diluted with water to 25mL in the 50mL volumetric flask, adds 2.5mLHNO
3(HNO
3Drip 0.5%KMnO before using
4Solution is to showing stable light red); The KSCN solution and the 2.5mL 10%SnCl that add 5mL 25% again
2Solution shakes up, and is diluted with water to 50mL, places 15min, surveys absorbance in the 430nm place with the 1cm cuvette.
Table 210%NaOH elution volume and Mo content
Last table accumulative total Mo total content is 5.7889g, and the recovery is 96.5%.In order to guarantee that as far as possible the Dowex-1 anion-exchange resin column does not contain Mo, when drip washing 1000mL, absorbance is under 0 the situation, again drip washing 200mL10%NaOH solution.
After 10%NaOH drip washing was intact, with distilled water that the NaOH flush away is extremely neutral, its leacheate absorbance was 0; Use the HCl drip washing 120-150mL of 2mol/L then, its leacheate absorbance is 0; Use the HNO of 3mol/L again
3Drip washing 100-120mL, its leacheate absorbance also is 0; At last with distilled water with HNO
3Flush away to leacheate is neutral, and its leacheate absorbance is 0.HCl leacheate, HNO
3The absorbance of leacheate and distilled water leacheate is 0 all, illustrates that their leacheate does not contain Mo.In addition, HNO
3Leacheate carries out ICP (inductively coupled plasma) after treatment and analyzes (detectability ppm level), its content consistent with blank sample (＜0.1ppm), this shows HNO
3The content that leacheate does not contain Mo or Mo seldom.
Above-mentioned experimental result shows that 10% NaOH solution can be with Na
2MoO
4Fully drip washing is got off, thereby guarantee in drip washing thereafter
99Do not contain Na in the Tc sample
2MoO
4
3)
99Tc
mRecovery test
99Tc
mRecovery test and simulation Mo target in the separation test of Mo identical, unique different be at Na
2MoO
4The Na that adds 7.5mCi on the solution before the anion-exchange column
2 99Tc
mO
4Upper prop again behind the solution.
In the detachment process of simulation Mo target, the HNO of the NaOH through 10%, the HCl of 2mol/L and 3mol/L
3After the drip washing, leacheate does not detect radioactivity, this explanation:
(1) 10% NaOH can not be with Na
2 99Tc
mO
4Drip washing is got off;
(2) HCl of 2mol/L can not be with Na
2 99Tc
mO
4Drip washing is got off;
(3) HNO of 3mol/L
3Can not be with Na
2 99Tc
mO
4Drip washing is got off.
Need to prove the HNO of 3mol/L especially
3Generally the drip washing from the anion-exchange column of most of metal examples can be got off, here earlier with the HNO of low concentration
3The HNO of high concentration is used in (3mol/L) drip washing again
3(7.5mol/L) drip washing Na
2 99Tc
mO
4Thereby, the HNO of assurance high concentration
3Do not contain other metal example in the leacheate, obtain highly purified Tc.
At HNO with 3mol/L
3After drip washing is intact, use the HNO of 7.5mol/L instead
3Drip washing 60-100mL is until Na
2 99Tc
mO
4Drip washing is got off fully.Use the Na of 7.5mCi simultaneously
2 99Tc
mO
4Make object of reference, calculate
99Tc
mThe recovery, its recovery＞99%.
4. the separation of irradiation Mo target
The dissolving of irradiation Mo target with separate fully with to simulate the Mo target the same.
1) dissolving of irradiation Mo target
Heavy 122.9g before No. 1 target dissolving, the heavy 119.6g in dissolving back, meltage is 3.3g; Heavy 119.0g before No. 2 target dissolvings, the heavy 116.2g in dissolving back, meltage is 2.8g, merges lysate, contains Mo 6.1g, the about 40mL of volume, control solution basicity is about 10%.
2) separation of irradiation Mo target
With the Dowex-1 anion-exchange resin column after transition on the above-mentioned merging lysate, use 10% NaOH drip washing then, flow speed control is about 0.5mL/min, and the NaOH elution volume is 1200mL; Then with the drip washing of about 100mL distilled water; Use the HCl drip washing of 150mL 2mol/L again; Then use the HNO of 120mL 3mol/L again
3Drip washing; Use the HNO of 7.5mol/L at last
3Drip washing 100mL is contained
98The Na of Tc
2TcO
4Solution.
Contain
98The Na of Tc
2TcO
4Solution evaporation is removed HNO
3After, add 2～3 HCl again and remove remaining HNO
3, add the 2mL dissolved in distilled water at last, contained
98The Na of Tc
2TcO
4Solution.The solution that takes a morsel is made the source, surveys gamma spectrum; Analyze the isotopics of technetium with inductively coupled plasma mass spectrometry meter (ICP-MS).Each isotopic abundance composition of technetium sees Table 3, and the content of Tc is 5.5 μ g, and its gamma spectrum as depicted in figs. 1 and 2.
The isotopic abundance of table 3 technetium is formed
Claims (9)
1. new radioactive nuclide of producing
98The method of TC is characterized in that mainly comprising following process:
(1) Mo target preparation: with the dimensioned Mo target sheet of Mo plate according to the accelerator target holder;
(2) Mo target irradiation: with d nuclear (
2H) irradiation bombardment Mo target is placed behind the irradiation and is no less than 270 days and enters dissolution process;
(3) irradiation Mo target dissolving: use commercially available H
2O
2Dissolving irradiation Mo target, H
2O
2Consumption by 2.5～5.0mL/gMo, fully the dissolving back adds the NaOH of weight concentration 9.5～10.5%, with Mo, the T after the dissolving
CConvert Na to
2MoO
4And Na
2T
CO
4, the consumption of NaOH is by 5.0～8.0mL/gMo, and the basicity of solution maintains 9.5～10.5%;
(4) Mo with
98Tc separates: contain
98T
CNa
2MoO
4Dowex-1 anion-exchange resin column on the solution is zero with NaOH drip washing to the Mo content in the leacheate of weight concentration 9.5～10.5%, removes NaOH with distilled water drip washing; Be the HCl drip washing of 1.5～2.5mol/L with 10.0～12.5 times of exchange column volumes, concentration respectively afterwards, 8.0～10.0 times of exchange column volumes, concentration are the HNO of 2～3mol/L
3Drip washing; The HNO that is 7.0～8.0mol/L with 5.0～8.0 times of concentration of exchange column volume at last
3Drip washing is contained
98The Na of Tc
2TcO
4Solution.
2. the radioactive nuclide of producing according to claim 2
98T
CMethod, it is characterized in that and will contain
98The Na of Tc
2TcO
4The solution heating evaporation is removed HNO
3, remove remaining HNO with HCl more afterwards
3, add dissolved in distilled water at last, obtain the Na of 0.1～0.2 times of exchange column volume
2 98Tc TO
4Solution.
3. the radioactive nuclide of producing according to claim 2
98T
CMethod, it is characterized in that described Dowex-1 anion-exchange resin column is the Dowex-1 anion-exchange resin column after handling through transition, handle described transition is behind anion-exchange column on the Dowex-1 resin, uses distilled water, HCl, distilled water, HNO successively
3, distilled water drip washing, use the NaOH drip washing of weight concentration 9.5～10.5% afterwards again, make the basicity of resin maintain 9.5～10.5%.
4. the radioactive nuclide of producing according to claim 3
98T
CMethod, it is characterized in that the Dowex-1 resin is for through cleaning, oven dry, grinding and screening is handled particle diameter at 80～120 purpose Dowex-1 resins.
5. the radioactive nuclide of producing according to claim 3
98T
CMethod, it is characterized in that on the Dowex-1 resin using HCl, distilled water, HNO successively behind the anion-exchange column
3, the distilled water cycling elution, cycle index is no less than 3 times, and the distilled water drip washing in the cycling elution, it is neutral that drip washing to leacheate is.
6. the radioactive nuclide of producing according to claim 5
98T
CMethod, it is characterized in that using successively HCl, distilled water, HNO
3, distilled water carries out cycling elution, rate of flow in rinse is controlled at 0.4～0.6mL/min.
7. according to the described radioactive nuclide of producing of one of claim 1 to 6
98T
CMethod, it is characterized in that the commercially available H of irradiation Mo target
2O
2At least dissolve H 2 times
2O
2Each consumption is 0.5～1.0mL/gMo, and total consumption is 2.5～5.0mL/gMo.
8. according to the described radioactive nuclide of producing of one of claim 1 to 6
98T
CMethod, it is characterized in that the NaOH drip washing of Dowex-1 anion-exchange resin column on the irradiation Mo target solution with weight concentration 9.5～10.5%, its rate of flow in rinse is controlled at 0.4～0.6mL/min.
9. the radioactive nuclide of producing according to claim 7
98T
CMethod, it is characterized in that the NaOH drip washing of Dowex-1 anion-exchange resin column on the irradiation Mo target solution with weight concentration 9.5～10.5%, its rate of flow in rinse is controlled at 0.4～0.6mL/min.
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|---|---|---|---|
| CN2010101743569A CN101866701B (en) | 2010-05-18 | 2010-05-18 | New method for preparing radionuclide 98Tc |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010101743569A CN101866701B (en) | 2010-05-18 | 2010-05-18 | New method for preparing radionuclide 98Tc |
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| CN101866701B CN101866701B (en) | 2012-07-04 |
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ID=42958376
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Cited By (9)
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| WO2012146586A1 (en) * | 2011-04-26 | 2012-11-01 | Technische Universität München | Method for producing starting material for a technetium generator |
| CN103733270A (en) * | 2011-04-10 | 2014-04-16 | 阿尔伯塔大学董事会 | Production of technetium from a molybdenum metal target |
| CN107210075A (en) * | 2015-02-09 | 2017-09-26 | 阿海珐有限公司 | Radionuclide generation system |
| CN108160988A (en) * | 2012-04-27 | 2018-06-15 | 加拿大国家粒子物理与核物理物理实验室 | The mthods, systems and devices produced for the cyclotron of technetium -99m |
| CN110335697A (en) * | 2019-07-11 | 2019-10-15 | 四川大学 | A kind of high abundance98The preparation method of Tc |
| CN111482452A (en) * | 2020-04-03 | 2020-08-04 | 武汉工程大学 | Gradient leaching technology of weathering crust elution-deposited rare earth ore residual leaching agent |
| CN111621645A (en) * | 2020-06-09 | 2020-09-04 | 西安迈斯拓扑科技有限公司 | Irradiation from accelerator100Mo production99mRecovery from Tc process effluent100Method for Mo |
| CN112885495A (en) * | 2019-11-29 | 2021-06-01 | 艾尔贝姆应用公司 | Method for producing Ac-225 from Ra-226 |
| CN113173595A (en) * | 2021-03-30 | 2021-07-27 | 广东回旋医药科技股份有限公司 | Preparation of cyclotron68Purification method of Ga crude product |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN103733270A (en) * | 2011-04-10 | 2014-04-16 | 阿尔伯塔大学董事会 | Production of technetium from a molybdenum metal target |
| WO2012146586A1 (en) * | 2011-04-26 | 2012-11-01 | Technische Universität München | Method for producing starting material for a technetium generator |
| CN108160988A (en) * | 2012-04-27 | 2018-06-15 | 加拿大国家粒子物理与核物理物理实验室 | The mthods, systems and devices produced for the cyclotron of technetium -99m |
| CN107210075A (en) * | 2015-02-09 | 2017-09-26 | 阿海珐有限公司 | Radionuclide generation system |
| CN110335697A (en) * | 2019-07-11 | 2019-10-15 | 四川大学 | A kind of high abundance98The preparation method of Tc |
| CN112885495A (en) * | 2019-11-29 | 2021-06-01 | 艾尔贝姆应用公司 | Method for producing Ac-225 from Ra-226 |
| CN112885495B (en) * | 2019-11-29 | 2022-09-13 | 艾尔贝姆应用公司 | Method for producing Ac-225 from Ra-226 |
| CN111482452A (en) * | 2020-04-03 | 2020-08-04 | 武汉工程大学 | Gradient leaching technology of weathering crust elution-deposited rare earth ore residual leaching agent |
| CN111482452B (en) * | 2020-04-03 | 2022-05-10 | 武汉工程大学 | Gradient leaching technology of weathering crust leaching type rare earth ore residual leaching agent |
| CN111621645A (en) * | 2020-06-09 | 2020-09-04 | 西安迈斯拓扑科技有限公司 | Irradiation from accelerator100Mo production99mRecovery from Tc process effluent100Method for Mo |
| CN113173595A (en) * | 2021-03-30 | 2021-07-27 | 广东回旋医药科技股份有限公司 | Preparation of cyclotron68Purification method of Ga crude product |
| CN113173595B (en) * | 2021-03-30 | 2023-09-15 | 广东回旋医药科技股份有限公司 | Cyclotron preparation 68 Purification method of Ga crude product |
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