Abstract: A system and method for eluting one or more radioisotope processing elements, such as generators and/or concentration and purification components, with a gas over eluent delivery mechanism is disclosed. The system is adapted to an elution/concentration system using two such mechanisms, one for an initial elution of one or more generators, and a second for "re-elution" of concentrated and purified radioisotope contained in a concentration subsystem. The operation of such a dual mechanism system may also be completely or partially automated. The invention also discloses a concentration subsystem containing all single-use components needed for concentration and/or purification, as a single use, self sealed, cartridge that can safely store waste eluate for safe and simple disposal.

Abstract: A process for producing substantially radio-impurity-free Bi-212 is disclosed. An acidic feed solution containing Pb-212 is contacted with an extraction medium to bind the Pb-212 thereto. The extraction medium is rinsed with a second acid solution to remove impurities therefrom, leaving a substantially impurity-free Pb-212-laden extraction medium The Pb-212 grows on the extraction medium to form Bi-212 by radioactive decay. The Bi-212 is then eluted from the extraction medium with an acid solution to form a substantially radio-impurity-free Bi-212 acid solution. An apparatus for carving out this process and a process for the therapeutic use thereof are also disclosed.

Abstract: A process for the production of yttrium-90, generated by radioactive decay of strontium-90, by means of a generator including a column containing strontium-90 adsorbed on a cation-exchange resin, wherein yttrium-90, the decay product of strontium-90, is obtained by the flow of an eluent through the resin column of the generator, an acetate buffer solution being used as the eluent. The process enables a solution to be obtained which is usable directly for labelling protein substrates, particularly monoclonal antibodies, with yttrium-90.

Abstract: A process for producing substantially impurity-free Bi-213 cations is disclosed. An aqueous acid feed solution containing Ac-225 cations is contacted with an ion exchange medium to bind the Ac-225 cations and form an Ac-225-laden ion exchange medium. The bound Ac-225 incubates on the ion exchange medium to form Bi-213 cations by radioactive decay. The Bi-213 cations are then recovered from the Ac-225-laden ion exchange medium to form a substantially impurity-free aqueous Bi-213 cation acid solution. An apparatus for carrying out this process is also disclosed.

Abstract: The present invention provides a shielding member for radioactive substances which can be made compact in size and light in weight while maintaining its shielding ability, or improves the shielding ability while keeping the same size, thereby to store a large volume of radioactivity. At the same time, the present invention provides a manufacturing method for the above shielding member and a radioactive solution-producing apparatus using the above shielding member. The radioactive substance-shielding member uses two or more kinds of radiation shielding materials of different shielding abilities. A shielding body made of a shielding material of the highest shielding ability is arranged at an area which is the nearest to a radioactive source.

Abstract: The present invention is a method of obtaining a radionuclide product selected from the group consisting of .sup.223 Ra and .sup.225 Ac, from a radionuclide "cow" of .sup.227 Ac or .sup.229 Th respectively. The method comprises the steps of a) permitting ingrowth of at least one radionuclide daughter from said radionuclide "cow" forming an ingrown mixture; b) insuring that the ingrown mixture is a nitric acid ingrown mixture; c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the "cow" from at least one radionuclide daughter; d) insuring that the at least one radionuclide daughter contains the radionuclide product; e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and f) recycling the at least one radionuclide daughter by adding it to the "cow". In one embodiment the radionuclide "cow" is the .sup.

Abstract: A .sup.99 Mo/.sup.99m Tc generator system includes a sorbent column loaded with a composition containing .sup.99 Mo. The sorbent column has an effluent end in fluid communication with an anion-exchange column for concentrating .sup.99m Tc eluted from the sorbent column.A method of preparing a concentrated solution of .sup.99m Tc includes the general steps of:a. providing a sorbent column loaded with a composition containing .sup.99 Mo, the sorbent column having an effluent end in fluid communication with an anion-exchange column;b. eluting the sorbent column with a salt solution to elute .sup.99m Tc from the sorbent and to trap and concentrate the eluted .sup.99m Tc on the ion-exchange column; andc. eluting the concentrated .sup.99m Tc from the ion-exchange column with a solution comprising a reductive complexing agent.

Abstract: A method of preparing a concentrated solution of a carrier-free radioisotope which includes the steps of:a. providing a generator column loaded with a composition containing a parent radioisotope;b. eluting the generator column with an eluent solution which includes a salt of a weak acid to elute a target daughter radioisotope from the generator column in a first eluate.c. eluting a cation-exchange column with the first eluate to exchange cations of the salt for hydrogen ions and to elute the target daughter radioisotope and a weak acid in a second eluate;d. eluting an anion-exchange column with the second eluate to trap and concentrate the target daughter radioisotope and to elute the weak acid solution therefrom; ande. eluting the concentrated target daughter radioisotope from the anion-exchange column with a saline solution.

Abstract: The separation of radon-220 from a liquid radioactive composition comprising radon-220, radium-224, and radium-225, and their daughter isotopes, as well as may be their thorium precursors, which liquid radioactive composition is adapted for use in the ultimate production of actinium-225 for radioimmunotherapy, can be achieved by treating the composition with a gas to strip the radon-220 from the composition.

Abstract: Apparatus and method for producing a radiopharmaceutical formulation utilize a radiation-shielding container for receiving a vial having the non-radioactive components necessary to form a radiopharmaceutical formulation therein. A mixture of such non-radioactive components and a radioactive liquid added thereto is both heated and cooled using a thermoelectric element. The container comprises a hollow outer shielding member formed from a radiation shielding material and a vial holder formed from a highly heat conductive material received therewithin. The vial holder includes a skirt portion that defines a socket. The socket is sized to receive in an intimate heat transmissive relationship a mounting projection that is itself connected in thermally conductive contact with the thermoelectric element.

Abstract: Methods and apparatus for producing selenium-72, separating it from its daughter isotope arsenic-72, and generating multiple portions of a solution containing arsenic-72 from a reusable parent substance comprised of selenium-72. The invention provides apparatus which can be located at a site where arsenic-72 is used, for purposes such as PET imaging, to produce arsenic-72 as needed, since the half-life of arsenic-72 is very short.

Abstract: The invention relates to a method of preparing a radiodiagnostic comprising a gaseous radionuclide formed by radioactive decay of a parent nuclide, by eluting with a suitable eluent the radioactive daughter nuclide from the parent nuclide provided ionically on a carrier, by using as a carrier for the parent nuclide ions a membrane, in particular an ion exchange membrane, past which the eluent is made to flow.The invention further relates to a radionuclide generator suitable for using said method.

Abstract: A method and a generator for separating daughter radioisotope from a stock solution containing the daughter radioisotope and its parent are provided. The generator is provided with a glass adsorbent which preferentially adsorbs daughter radioisotope relative to the parent radioisotope and circulation means for withdrawing the stock solution from a reservoir, contacting the solution with the glass adsorbent to adsorb the daughter radioisotope and returning the parent radioisotope-enriched solution to the reservoir. In the process stock solution containing daughter radioisotope having a predetermined pH is contacted with the glass adsorbent to selectively adsorb the daughter radioisotope thereon and the daughter radioisotope is eluted with an eluant at a second predetermined pH. The process also includes a step of washing the glass adsorbent with a wash solution at the first predetermined pH to remove traces of the parent radioisotope from the adsorbent prior to eluting the daughter radioiotope.

Abstract: A radionuclide generator of the type having a column with an inlet port and an outlet port, means for connecting the inlet port of the column to a source of eluant, and means for connecting the outlet port to an eluate collection vessel, further includes a plug removably mounted to the inlet connecting means to seal the same and a cover removably mounted to the outlet connecting means. The outlet cover has a vent therein whereby gases produced during the sterilization of the generator are vented.

Abstract: Water soluble irradiation targets are disclosed for the production of .sup.186 Re and .sup.188 Re. The irradiation targets are selected for both water solubility and absence of elements which would produce contaminating isotopes for medical therapeutic and diagnostic use. In one embodiment, .sup.186 Re or .sup.188 Re is produced by the direct irradiation of a water soluble irradiation target comprising .sup.185 Re or .sup.187 Re, respectively. Preferred targets for this purpose include aluminum perrhenate, lithium perrhenate and magnesium perrhenate. In another embodiment, a zirconyl tungstate generator comprising .sup.188 W for the production of .sup.186 Re is obtained by irradiating a soluble irradiation target comprising .sup.186 W, dissolving the irradiated target in aqueous solution, reacting the dissolved target with an aqueous solution comprising zirconyl ion to form an insoluble zirconium tungstate precipitate and disposing the precipitate in an elutable container.

Abstract: The automatic radioisotope filling apparatus of the present invention is equipped with a radioisotope vial containing a radioisotope solution, a saline vial containing a physiological saline solution, a dilution vial to which a predetermined amount of the radioisotope solution and a predetermined amount of the physiological saline solution are to be transferred to prepare a diluted radioisotope solution, a radiation detector for measuring the radioactive intensity of the diluted radioisotope solution prepared in the dilution vial, and a plurality of label vials containing a drug to be labeled.

Abstract: A method and generator for preparing the radioisotope of lead, .sup.212 Pb, whereby .sup.228 Th, in a closed chamber, is allowed to decay to gaseous .sup.220 Rn which is then readily separated from the thorium and other decay products by diffusing the .sup.220 Rn gas into a second chamber, where it decays to .sup.212 Pb which can then be collected from the second chamber. The .sup.228 Th preferably is amorphous, such as thorium stearate. Collection of .sup.212 Pb occurs in a medium of high and open porosity into which the .sup.220 Rn diffuses so that the decay products recoil into the medium. The .sup.212 Pb can be recovered from this medium by dissolving the medium or by reacting it with an antibody-chelating complex solution to entrap it in the antibody-chelating complex.

Abstract: Improved radionuclide generators include a substantially insoluble salt of a parent radionuclide precursor which may be directly irradiated and then packed in a column for subsequent elution of the daughter radionuclide without the production of counter ion isotopic contaminants. The parent radionuclide precursor is provided in the form of an insoluble salt of the parent element whose counter ion, preferably aluminum, forms a relatively soluble salt with the desired daughter radionuclide. The improved generators may be prepared by reacting a parent radionuclide precursor with aluminum to obtain an aluminum salt of the precursor having low solubility in water, irradiating the aluminum salt to obtain an irradiated aluminum salt of the parent radionuclide, and then disposing the irradiated parent radionuclide in an elutable container. Useful parent radionuclide precursors include molybdenum-98 in the form of molybdate for the production of daughter .sup.

Abstract: There is provided a generator for short-lived radionuclides. The generator comprises a support, an ion-exchange agent and a parent radionuclide in a steady-state equilibrium with a daughter nuclide, which daughter nuclide can be selectively eluted from said column. A suitable parent radionuclide is .sup.191 OS in equilibrium with .sup.191m Ir. There is also provided a specific Os(VI) complex which has certain advantages.

Abstract: A process for preparing a tungsten-188/rhenium-188 generator having a tungstate matrix containing W-188 produced by irradiating tungsten-186 in the tungstate compound. High activity, carrier-free rhenium-188 may be obtained by elution. Substrates for further purifying the rhenium-188 eluate are also described.

Abstract: An automatic radioisotope filling apparatus which includes a radioisotope vial containing a radioisotope solution, a saline vial containing a physiological saline solution and a plurality of label vials containing a drug into which a predetermined amount of the radioisotope solution or the physiological saline solution is to be filled automatically. A required amount of the radioisotope solution or the physiological saline solution is automatically metered and automatically filled into each label vial and consequently the radiation exposure of the operator of the apparatus is minimized.

Abstract: Silica gels modified with amino groups or magnesium silicates are suitable carrier materials for technetium-99m generators since they retain copper(II) ions well and thus produce a copper-free eluate.

Abstract: A system for eluting a daughter radioisotope from a parent radioisotope and containerizing the resultant eluate in an evacuated container having a rubber stopper, providing for delivery of eluant from a reservoir through a tube to a generator containing the parent radioisotope, for venting of the reservoir to atmosphere via a tube, and for delivery of eluate from the generator via a tube to a tubular needle pierced through the stopper, with a cam-controlled hinged pinch plate for pinching the tubes closed.

Abstract: A generator of radionuclides comprises a generator column (10) containing the radionuclide and provided with an inlet (12) and an outlet (14) for eluent, first and second reservoirs (16, 18) for eluent, and connecting means for passing a pre-determined column of eluent from the second reservoir through the generator column. A part defining the second reservoir, which part may be the second reservoir itself, is rotatable to determine the volume of eluent passed through the column. The second reservoir is preferably shaped as a sector of a cylinder rotatable around a horizontal axis.The generator is well suited for vacuum elution of a variable pre-determined volume of eluent into a single size collection vial with subsequent drying of the generator column.

Abstract: This invention relates to a standard component .sup.99m TC elution generator useful for medical purposes and consisting of prefabricated component parts. The main generator column of the device may be used both as an irradiation container and an elution container, enabling the user to supply activated or nonactivated parts. The main generator column made from by neutrns little activable materials serves first as reactor irradiation ampoule and after having been activated in the reactor by neutrons and after a simple adjustment serves directly as the generator column. It is filled with water insoluable molybdates or polymolybdates (with the molybdenum content in the range 10-40%), easily releasing .sup.99m Tc generated by radioactive decay of the mother .sup.99 Mo formed in it by neutron activation. This column filling serves originally as target material for reactor irradiations and afterwards it is directly used as the generator elution matrix.

Abstract: An alpha recoil ion-implantation method and apparatus are described which use an alpha-emitting source that is a radioactive parent of the daughter isotope of interest to implant into a suitable substrate the recoil daughter ions resulting from alpha decay of the parent. For example, a .sup.241 Am source in thin layer form is placed next to a substrate such as a solid state track recorder in a vacuum which houses an assembly for rotating opposing disks receiving the alpha-emitting source and the substrate, respectively. Each alpha decay of .sup.241 Am results in a .sup.237 Np ion with enough recoil energy to be implanted into the substrate. Fissionable deposits of .sup.239 Pu, .sup.235 U, and .sup.238 U can also be made by this method and apparatus.

Abstract: Potassium osmate, of the formula K.sub.2 Os O.sub.2 (OH).sub.4), used to make a column for the generation of Ir-191 m, which is used in first pass angiography to detect cardiac defects in patients.

Abstract: A radon sampling unit comprising a cylindrical body containing a measured amount of charcoal for collecting and holding radon gas. A fine mesh screen is frictionally held on top of the charcoal by a retaining ring engageable with the inner sidewall of said body. The lid is screw threaded and hermetically sealed to the body. A layer of dessicant is frictionally held inside the body vertically spaced above the charcoal. The cylindrical body has a plurality of alternate lugs on top thereof at different heights and a retaining metallic ring which serves as a unique method of retention of the lid assembly to the body. The cylindrical body may be modified by having an interior spirally wound metallic sheet to vary the inner diameter of the body as desired.

Abstract: A generator system to provide iridium-191m for clinical imaging applications comprises an activated carbon adsorbent loaded with a compound containing the parent nuclide, osmium-191. The generator, which has a shelf-life in excess of two weeks and does not require a scavenger column, can be eluted with physiologically compatible saline.

Abstract: Quantities of radioactive material are dispersed at a user location. Billing is accomplished by monitoring the decay of material and the degree of activity following each user withdrawal.

Abstract: A method, composition of matter, and apparatus for producing substantially pure Ag-109m for use in biomedical imaging techniques. Cd-109, which decays with a half-life of 453 days to Ag-109m is loaded onto an ion exchange column consisting of particulate tin phosphate. After secular equilibrium is reached in about ten minutes, Ag-109m may be selectively eluted from the column by means of a physiologically acceptable aqueous buffered eluent solution of sodium thiosulfate, and either ascorbic acid or dextrose. The breakthrough of toxic Cd-109 is on the order of 1.times.10.sup.-7, which is sufficiently low to permit administration of the Ag-109m-containing eluate, with but a minor pH adjustment, directly to a human patient within a matter of seconds.

Abstract: A method and apparatus for providing radionuclides of bismuth-212 and lead-212. Thorium-228 and carrier solution starting material is input to a radiologically contained portion of an isotopic generator system, and radium-224 is separated from thorium-228 which is retained by a strongly basic anion exchange column. The separated radium-224 is transferred to an accessible, strongly acidic cationic exchange column. The cationic column retains the radium-224, and natural radioactive decay generates bismuth-212 and lead-212. The cationic exchange column can also be separated from the contained portion of the system and utilized without the extraordinary safety measures necessary in the contained portion. Furthermore, the cationic exchange column provides over a relatively long time period the short lived lead-212 and bismuth-212 radionuclides which are useful for a variety of medical therapies.

Abstract: A method for preparing a .sup.195m Au-containing liquid is provided. In the method, .sup.195m Hg is adsorbed on an adsorption agent and then the daughter radioisotope .sup.195m Au is eluted from the adsorption agent with an eluant containing a gold-complexing agent. The adsorption agent comprises a mercury ion-binding material having a substantially stronger adsorption affinity for mercury ions than for gold ions.Also disclosed are a radioisotope generator capable of producing a .sup.195m Au-containing liquid and a process for conducting a radiodiagnostic examination on a warm-blooded animal using a .sup.195m Au-containing liquid.

Abstract: For the radiation-proof elution and metering of a radioactive nuclide from a nuclide generator into a stock ampoule, the generator located in a radiation-proof housing is connected, on the one hand, to a stock of liquid nuclide solvent and, on the other hand, to an aspiration and metering device, connected to a filling mechanism, for the eluate.

Abstract: A generator of radionuclides such as technetium-99m comprises a generator column (10) containing the radionuclide, a first reservoir (16) for eluent, a second reservoir (18) to contain a volume of the eluent required for a single elution, and a vessel 40 to contain eluate. First, a pre-set volume of eluent is transferred from the first to the second reservoir; then the eluent is sucked from the second reservoir through the column into the eluate vessel. A hydrophobic filter 32 adjacent the second reservoir (18) permits the use of air to dry the column (10) and to bring the partly filled eluate vessel (40) to atmospheric pressure.

Abstract: Sampling devices for detecting particulate contaminants, particularly radioactive particulate contaminants, in a gaseous medium, such as air. The devices use filters comprising a filter membrane sandwiched between two pieces of plastic material having holes exposing the filter membrane to the gaseous medium. Each filter is moved between a sampling position at which the filter is exposed to the gaseous medium and a measurement position at which the amount of particulate material collected by the filter can be measured. In the measurement position, a gas-tight seal may be formed with the plastic surrounding the filter medium so that the chamber holding the filter may be evacuated for measurement of radioactive particles. The filter may be moved linearly or rotationally. The detector may comprise a detector of radioactive particles.

Abstract: A method for preparing a .sup.195m Au-containing liquid is provided. In the method, .sup.195m Hg is adsorbed on an adsorption agent and then the daughter radioisotope .sup.195m Au is eluted from the adsorption agent with an eluant containing a gold-complexing agent. The adsorption agent comprises a mercury ion-binding material having a substantially stronger adsorption affinity for mercury ions than for gold ions.Also disclosed are a radioisotope generator capable of producing a .sup.195m Au-containing liquid and a process for conducting a radiodiagnostic examination on a warm-blooded animal using a .sup.195m Au-containing liquid.

Abstract: An electronic device for rapidly determining the concentration (i.e. mCi/cc) of radioactivity in a closed container, and for determining the volume of material needed to be removed such that the removed volume will constitute a predetermined amount of radioactivity, is disclosed; the device further incorporating novel features so that said determinations, and actual withdrawal of the desired amount radioactivity material may be accomplished without removing the closed container from its leaded radiation shield. This device also has provision for determining the percentage relationship of Molybdenum impurities in Technetium .sup.99M, and further provided an electro-mechanical carrousel-type means for systematically positioning multiple source containers as desired by the user thereof.

Abstract: A composition comprising .sup.82 Sr and an adsorbant selected from the group consisting of tin oxide, hydrated tin oxide, polyantimonic acid, titanium oxide, and ferric oxide.A low .sup.82 Sr breakthrough method of generating .sup.82 Rb from a .sup.82 Sr charged adsorbant comprising eluting wherein said adsorbant is selected from the group consisting of tin oxide, polyantimonic acid, titanium oxide, ferric oxide, and hydrated tin oxide.

Abstract: Disclosed is a radioisotope generator useful in the process of eluting a daughter radioisotope from an adsorbed parent radioisotope. The radioisotope generator comprises a column containing carrier material adapted to adsorb the parent radioisotope and including an inlet opening and an outlet opening. The outlet opening of the column is connected to a tapping point on the generator by an eluate conduit, the tapping point adapted to receive an evaluated elution vial so that a liquid eluate containing the daughter radioisotope can be obtained from the generator under vacuum. The generator further includes a device for interrupting the elution process before the elution vial is entirely filled while simultaneously exposing the generator to sterile air both in the direction of the generator column and of the elution vial.

Abstract: A method of preparing a solution of gallium 68 from germanium 68, wherein the germanium 68 is fixed on particles of tin dioxide and the gallium 68 produced by radioactive decay of the germanium 68 fixed on said particles is then eluted with a solution of hydrochloric acid.

Abstract: A method for generating Ga-68 from Ge-68 is provided that comprises contacting a substrate on which Ge-68 has been adsorbed with an alkaline solution having a pH of at least about 12 and thereby eluting Ga-68. Preferably the Ga-68 is eluted in the form of the gallate ion. A generator system comprises a generator column containing Ge-68 and Ga-68, a sealed eluant container having a predetermined quantity of eluant comprising an alkaline solution having a pH of at least about 12, and an evacuated eluate collection vial having a vacuum sufficient to draw the desired quantity of eluate into the eluate collection vial. The eluate collection vial can contain a neutralizing agent and also a diagnostically useful complexing agent.

Abstract: A system for eluting a daughter radioisotope from a parent radioisotope and containerizing the resultant eluate in an evacuated container having a rubber stopper, providing for delivery of eluant from a reservoir through a charge of the parent radioisotope in a generator and thence to a tubular needle adapted to be pierced through the stopper of the evacuated container for suctioning the eluant from the sealed eluant supply into the generator and for suctioning the resultant eluate into the container. The needle is at the lower end of a valve body having a valve plug rotatable therein between a closed and open position. The plug is adapted to be pushed down to push the valve body down to cause the needle to pierce the stopper, after which the plug is rotated to open position, in which it effects venting of the eluant reservoir to atmosphere, delivery of eluant from the reservoir to the generator, and delivery of eluate from the generator to the needle.

Abstract: A physiologically acceptable solution of gallium-68 fluorides, having an activity of 0.1 to 50 millicuries per milliliter of solution is provided. The solution is obtained from a generator comprising germanium-68 hexafluoride bound to a column of an anion exchange resin which forms gallium-68 in situ by eluting the column with an acid solution to form a solution containing .sup.68 Ga-fluorides. The solution then is neutralized prior to administration.

Abstract: A Technetium-99m generator has a matrix having a compound of molybdenum-99 bound into or forming the matrix, the compound of the molybdenum-99 being substantially insoluble in an eluant which can be used in a radiopharmaceutical and the molybdenum compound permitting diffusion of technetium-99m therethrough and elution therefrom. The molybdenum compound can be a monomolybdate, an isopolymolybdate or a heteropolymolybdate and zirconium molybdate is preferred although other cation molybdates may be used. Methods of preparation of the generator include dissolving irradiated molybdenum trioxide in alkaline solution and precipitating the molybdate at a selected pH and packing the precipitate in finely divided form into a column. Alternatively the generator may be formed from a non-radioactive, molybdenum compound and activated later when desired by passing a solution of a compound of molybdenum-99 through the column.

Abstract: An electronic device for rapidly determining the volume of a radioactive gas needed to be removed from a closed container such that the removed volume will constitute a predetermined amount of radioactivity. Further, the device incorporates novel features including the use of a shielded valve assembly so that this determination, and actual withdrawal of the desired amount of radioactive gas may be accomplished without removing the closed container from its leaded radiation shield. The leaded radiation shield also serves as a shipping container for the multidose radioactive gas container, and is easily removed for periodic interchange with similarly shielded replacement radioactive source containers. The shielded valve assembly attaches to the top of the shielded closed container to facilitate withdrawal with minimum radiation exposure to the handling operator.

Abstract: A generator for obtaining radioactive gallium-68 from germanium-68 bound in a resin containing unsubstituted phenolic hydroxyl groups. The germanium-68 is loaded into the resin from an aqueous solution of the germanium-68. A physiologically acceptable solution of gallium-68 having an activity of 0.1 to 50 millicuries per milliliter of gallium-68 solution is obtained. The solution is obtained from the bound germanium-68 which forms gallium-68 in situ by eluting the column with a hydrochloric acid solution to form an acidic solution of gallium-68. The acidic solution of gallium-68 can be neutralized.

Abstract: The radiation shielding surrounding a radionuclide generator of the parent-daughter type can be minimized if the containing means used to contain the support medium onto which is adsorbed the parent nuclide defines a curved path.

Abstract: A generator for liquid containing .sup.99m Tc has an adsorbant bed of alumina, zirconia or the like and has associated therewith a quantity of an electron scavenging compound of a rare earth, silver or gold so as to maintain elution efficiency during the working life of the generator. The compound may be a rare earth oxide such as ceric oxide typically present as a coating on alumina particles in an amount of about 0.1% by weight or a compound such as silver chloride present in quantities typically of about 5%. The eluant may be sodium or potassium perchlorate in water.

Abstract: Nuclide generators for preparing sterile and pyrogen-free radioactive solutions consist of a generator column which is provided with radiation shielding and connected to a container for eluting agent and has a connection to a container for eluate. The generator and the container for eluting agent are located in vessels with centering devices, wherein the generator column with its radiation shielding is located in a fixed position relative to the vessel between two centering devices and connected via a cannula to the container for eluting agent which is held in a recess of one centering device in a fixed position relative to the generator column. The other centering device has also a recess for guiding and holding the eluate container which is connected to the generator column via a cannula.