CN204516369U - radionuclide generator device - Google Patents

radionuclide generator device Download PDF

Info

Publication number
CN204516369U
CN204516369U CN201520212161.7U CN201520212161U CN204516369U CN 204516369 U CN204516369 U CN 204516369U CN 201520212161 U CN201520212161 U CN 201520212161U CN 204516369 U CN204516369 U CN 204516369U
Authority
CN
China
Prior art keywords
ion exchange
exchange column
generator device
chromatographic column
radionuclide generator
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
CN201520212161.7U
Other languages
Chinese (zh)
Inventor
塞威利娜·范德沃尔德
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.)
Ire Environment And Life Sci-Tech Co
Original Assignee
Ire Environment And Life Sci-Tech Co
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 Ire Environment And Life Sci-Tech Co filed Critical Ire Environment And Life Sci-Tech Co
Priority to CN201520212161.7U priority Critical patent/CN204516369U/en
Application granted granted Critical
Publication of CN204516369U publication Critical patent/CN204516369U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Landscapes

  • Treatment Of Liquids With Adsorbents In General (AREA)

Abstract

Be suitable for the radionuclide generator device being produced carrier-free rhenium-188 Re-188 by tungsten-188W-188, described device comprise be arranged to be mounted with inorganic adsorbent chromatographic column, for comprising the inlet tube of alkali-metal eluent and the outlet for eluate, described chromatographic column is made up of stainless steel, and has at least 40cm 3volume and between 5 to the height of 15cm.

Description

Radionuclide generator device
Technical field
A kind of radionuclide generator device for being produced rhenium-188 (Re-188) by tungsten-188 (W-188).
Background technology
Penetrating property labeling process enables Re-188 be used in treatment use, and condition provides Re-188 with suitable concentration in predetermined volumetric injection.
The decay of W-188 enables its daughter isotope produce Re-188.Known Re-188 has the half life period of 19.9 hours, and this described isotopic preparation giving to apply for foreign treatment is with difficulty.For this reason, the user itself being used for the treatment of the Re-188 of purposes to hope generation provides radionuclide generator device to be favourable.
US 5,186,913 discloses a kind of for providing generator system and the method for generation thereof of the carrier-free Re-188 of perrhenic acid form.
Patent US 5,186, generator system disclosed in 913 comprises the W-188/Re-188 generator post with Stationary liquid, accommodates W-188 and Re-188 in W-188/Re-188 generator post.Made it possible at salt perrhenic acid sodium (NaReO by chromatographic column wash-out sodium chloride (NaCl) 4) optionally wash-out Re-188 under form.
Generator system also comprises can produce perrhenic acid (HReO 4) ion exchange column, ion exchange column is in the end by by being combined the neutral substance of ion exchange column and analogous protein and analog and being used to therapeutical uses.
In addition, produce in post and perform by this radioisotopic reactor can be generated as raw-material W-188.Dissimilar reactor can produce W-188, but the intrinsic specific activity of W-188 will depend on used reactor.
The isotopic quantity held in the quality of radioisotopic intrinsic specific activity and product (that is, W-188) is relevant.So if intrinsic specific activity is very high, the isotopic quantity in the quality of product is also high, this is conducive to producing concentrated carrier-free Re-188.
The size that US 5,186,913 teaches post can be generally 1x3.5 centimetre, this means that in post, produce W-188 is realized by high intrinsic specific activity (3.5mCi/mg (millicurie/milligram)).
This means that in post, produce starting material needs specific reactor, specific reactor can for very expensive the consumer itself that hope produces Re-188.Described document shows, the size of post is inversely proportional to the intrinsic specific activity of the W-188 depending on used reactor.
But, be, as the intrinsic specific activity being arranged on the W-188 in post lower (such as, lower than 3mCi/mg), how to produce Re-188 for treatment use disclosed in described document does not have.The reactor that therefore user is limited to use expensive is provided as raw-material W-188 in systems in which.
In addition, US 5,186,913 does not consider that daughter isotope Re-188 may be polluted by parent isotope Re-188 during wash-out.For this reason, do not get rid of elution efficiency low, this produces other kind be not allowed to for treatment use by causing in generation Re-188 and the solution obtained.
Summary of the invention
Therefore, need to provide a kind of radionuclide generator device, described radionuclide generator device can effectively and simultaneously by reducing to produce Re-188 with daughter isotope contaminated relevant risk between processing period.
For this reason, the invention provides a kind of radionuclide generator device of preamble according to claim 1, it is characterized in that, chromatographic column is made up of stainless steel, and described chromatographic column has at least 40cm 3volume (volume) and between 5 to the height of 15cm.
Unexpectedly observe, the chromatographic column be made up of stainless steel makes it possible to produce Re-188 by reducing Re-188 at wash-out (elution) period contaminated risk cause W-188.In addition, the post be made up of stainless steel has suitable length and radiation hardness.Height and the volume of chromatographic column of the present invention contribute to the above-mentioned effect relevant with the pollution reducing daughter isotope.
The height of chromatographic column and the advantage of volume are, relative to the post of prior art, can produce the W-188 of greater number in post.
As mentioned above, height and its volume of post make it possible to use to generate compared with the W-188 generated by other specific reactor to have compared with the reactor as raw-material W-188 of low-activity than degree.
Therefore, by using height between the chromatographic column of 5 to 15cm and the risk of pollution simultaneously by reducing daughter isotope is come effectively and reliably generation carrier-free Re-188.
More preferably, inlet tube and outlet are also made up of stainless steel.
Advantageously, radionuclide generator device comprises concentrator apparatus, described concentrator apparatus has the first ion exchange column and the second ion exchange column successively, described first ion exchange column has the first port and the second port, described first port is connected to the outlet of chromatographic column, described second port is connected to the upstream open of described second ion exchange column, and described second ion exchange column has downstream opening.
Work as NaReO 4when being produced by chromatographic column of the present invention, the amount of eluent (eluent) makes a large amount of NaReO 4be received, this is not easy to therapeutical uses, because the injection of product needs to be accommodated in suitable volumetric injection.
For this reason and according to for generation of NaReO 4method, advantageously Re-188 is concentrated in and is convenient in the less volume of therapeutical uses.
First ion exchange column and the second ion exchange column comprise Stationary liquid with optionally isolating ions.So the first ion exchange column makes it possible to discharge high rhenium ion (ReO -), and the second ion exchange column makes it possible to high rhenium ion is fixed on Stationary liquid to be concentrated in volume little compared with the volume of chromatographic column by high rhenium ion.This causes producing Re-188 in the suitable volumetric injection that can be used in treatment use.
In a particular embodiment, concentrator apparatus is disposable concentrator apparatus.
Preferably, the connection between the first ion exchange column and chromatographic column and the connection between the first ion exchange column and the second ion exchange column are obtained by disposable insert and disposable valve.
Accompanying drawing explanation
Other embodiment according to device of the present invention is refer in claims.
Fig. 1 shows according to radionuclide generator device of the present invention;
Fig. 2 shows according to chromatographic column of the present invention;
Fig. 3 shows according to concentrator apparatus of the present invention.
Embodiment
Radionuclide generator device 1 (Fig. 1) according to the present invention is suitable for utilizing chromatographic column to produce carrier-free Re-188 by W-188 for treatment use, and chromatographic column is made up of stainless steel and is had at least 40cm 3, preferably 56cm 3volume and between 5 to the height (Fig. 2) of 15cm.
Radionuclide generator device 1 comprises chromatographic column 2, and chromatographic column 2 is arranged to be mounted with inorganic adsorbent, and has for the inlet tube 4 of eluent (preferably, the alkaline metal of such as NaCl and so on) and the outlet for eluate.The structure of radionuclide generator device 1 can mixed structure (Fig. 1) be surrounded chromatographic column 2 and environment to be isolated in the finite space.
More specifically, when chromatographic column 2 is mounted with Stationary liquid, W-188 is arranged on Stationary liquid and Re-188 is produced continuously by parent isotope.
The NaReO collecting scheduled volume (apredetermined volume) at the outlet place of post 2 is made it possible to by chromatographic column 2 wash-out NaCl 4.
Chromatographic column 2 can be connected to the concentrator apparatus (Fig. 3) with the first ion exchange column 6 and the second ion exchange column 7.
First ion exchange column 6 has the first port 8, second port 9 and Stationary liquid.Second ion exchange column 7 have upstream open 10 and for eluate downstream opening 11 and there is Stationary liquid.
Advantageously, the connection between chromatographic column 2 and concentrator apparatus can be connected with the first port 8 of the first ion exchange column 6 by the outlet of the eluate by being used for chromatographic column and to realize.In addition, the first ion exchange column can also be connected to the upstream open 10 of the second ion exchange column 7 by its second port 9.Those acquisition by the existence of insert and valve are connected and ensure that the fluid between each post is communicated with.
Like that, when concentrator apparatus is attached to radionuclide generator device 1 by insert and pipe, eluent can be introduced into by the inlet tube 4 of chromatographic column 2 and advance on the second ion exchange column 7.Then, carrier-free Re-188 can be collected from downstream opening 11.
More accurately, when chromatographic column 2 connects with concentrator apparatus, NaReO 4arrive the first ion exchange column 6 and high rhenium ion (ReO 4-) be released.So, ReO 4-arrive the second ion exchange column 7, wherein, ReO 4-be fixed in the fixing matrix of such as anion-exchange column and so on.
The advantage of concentrator apparatus of the present invention is: the concentration achieving high rhenium ion with the less volume in the second ion exchange column 7.Described less volume is less than the volume in chromatographic column.Like that, in suitable volumetric injection, produce Re-188 with suitable concentration, therefore Re-188 can be directly used in treatment use.
Although disclose the preferred embodiments of the present invention for illustrative purposes, it will be understood by those skilled in the art that, when not exceeding scope and spirit of the present invention disclosed in claims, multiple amendment, interpolation and replacement are possible.

Claims (4)

1. be suitable for the radionuclide generator device being produced carrier-free rhenium-188 by tungsten-188, this radionuclide generator device comprise be arranged to be mounted with inorganic adsorbent chromatographic column, for comprising the inlet tube of alkali-metal eluent and the outlet for eluate, it is characterized in that, described chromatographic column is made up of stainless steel, and has at least 40cm 3volume and between 5 to the height of 15cm.
2. radionuclide generator device according to claim 1, this radionuclide generator device comprises concentrator apparatus, described concentrator apparatus has the first ion exchange column and the second ion exchange column successively, described first ion exchange column has the first port and the second port, described first port is connected to the outlet of described chromatographic column, described second port is connected to the upstream open of described second ion exchange column, and described second ion exchange column has downstream opening.
3. radionuclide generator device according to claim 2, wherein, described concentrator apparatus is disposable concentrator apparatus.
4. radionuclide generator device according to claim 2, wherein, the connection between described first ion exchange column and described chromatographic column and the connection between described first ion exchange column and described second ion exchange column are obtained by disposable insert and disposable valve.
CN201520212161.7U 2015-04-09 2015-04-09 radionuclide generator device Active CN204516369U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201520212161.7U CN204516369U (en) 2015-04-09 2015-04-09 radionuclide generator device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201520212161.7U CN204516369U (en) 2015-04-09 2015-04-09 radionuclide generator device

Publications (1)

Publication Number Publication Date
CN204516369U true CN204516369U (en) 2015-07-29

Family

ID=53714317

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201520212161.7U Active CN204516369U (en) 2015-04-09 2015-04-09 radionuclide generator device

Country Status (1)

Country Link
CN (1) CN204516369U (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2021168557A1 (en) * 2020-02-24 2021-09-02 Jubilant Draximage Inc. Generator columns for elution systems loaded with pre-charged matrix

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2021168557A1 (en) * 2020-02-24 2021-09-02 Jubilant Draximage Inc. Generator columns for elution systems loaded with pre-charged matrix

Similar Documents

Publication Publication Date Title
JP7034107B2 (en) Radioisotope concentrator
Martini et al. A solvent-extraction module for cyclotron production of high-purity technetium-99m
US5186913A (en) Tungsten-188/carrier-free rhenium-188 perrhenic acid generator system
Loktionova et al. Improved column-based radiochemical processing of the generator produced 68Ga
JPS60194399A (en) Method of treating initial pertechnetium acid salt aqueous solution
CN204516369U (en) radionuclide generator device
Viglašová et al. Column studies for the separation of 99m Tc using activated carbon
CA1057946A (en) 82sr-82rb radioisotope generator
Andersson et al. Robust high-yield~ 1 TBq production of cyclotron based sodium [99mTc] pertechnetate
US5729821A (en) Concentration of perrhenate and pertechnetate solutions
CN103263849A (en) Rapid separation method of activated product gallium in fission product
RU158401U1 (en) RADIONUCLIDE GENERATOR DEVICE
CN108031288B (en) Method for simultaneously producing radioactive strontium-90 and cesium-137 by adopting centrifugal extractor
Pao et al. A new method for the preparation of 68 Ga-generators following proton bombardment of gallium oxide targets
CN211455322U (en) Actinium-225 nuclide purifying device
Chattopadhyay et al. Separation of pertechnetate from molybdate by anion-exchange chromatography: recovery of 99mTc from (n, γ) 99Mo and suitability for use in central radiopharmacy (CRPh)
Keddadouche et al. Design and performance of an automated chemical extraction bench for the preparation of 10Be and 26Al targets to be analyzed by accelerator mass spectrometry
ZA202100079B (en) System and method for evaluating elution efficiency and radiopurity of tc-99m generators
Aardaneh et al. Radiochemical separation of 67 Ga from Zn and Cu using the adsorbent resin Amberlite XAD-7
Ruiz Quiros A Chromatographic Method to Separate Sc (III) from Zn (II) Ions: A Step in the Purification of Sc-44 (an isotope of medical interest)
Teranishi et al. 113 Sn-113m In generator with a glass beads column
Jang et al. A quantitative description of the compatibility of technetium-selective chromatographic technetium-99m separation with low specific activity molybdenum-99
Kim et al. Evaluating the effect of ammonium ions on the separation efficiency of two adjacent lanthanides
Aardaneh et al. Radiochemical separation of 82 Sr and the preparation of a sterile 82 Sr/82 Rb generator column
Andronov et al. Sorption conditioning of eluate of 68 Ge/68 Ga generator for medical purposes

Legal Events

Date Code Title Description
C14 Grant of patent or utility model
GR01 Patent grant