摘要:
A multi-vial dispensing cassette provides serial dispensement into a plurality of dispense vials. Needle holders may be provided for one or more vials in the cassette and at clip may be incorporated into the needle holder.
摘要:
Disclosed herein is an radioisotope adsorbent including a bifunctional organosilane compound, including an organosiloxane functional group and a phosphate group, bonded on the surface of silica which is a bone structure of the adsorbent, and a method of preparing the radioisotope adsorbent, and a strontium/yttrium generator using the radioisotope adsorbent. Since the radioisotope adsorbent has a high adsorption capacity for 90Y such as 95% extraction efficiency or more from ICi 90Sr/90Y by using a column packed with 0.4 g of the adsorbent with a high-purity of 90Y, it can be usefully to be employed in the fields requiring 90Y.
摘要:
A slurry dispensing system (10) is disclosed. A peristaltic pump (28) may direct a flow of slurry out of a horizontal mixer (20) to a slurry dispenser (140). This slurry dispenser (140) may be operated on a programmed manner by a controller (260) to dispense slurry into a container (36). Both a bypass valve (172) and a dispensing valve (204) of the slurry dispenser may be opened/closed on a programmed basis by the controller (260) to deliver slurry to a container (36), such as a glass column. Slurry may be intermittently directed into a metering chamber (194) of the slurry dispenser (140), while the remainder of the slurry being directed into the slurry dispenser (140) may be recirculated back to the horizontal mixer (20).
摘要:
The present invention provides a method for the generation of 223 Ra of pharmaceutically tolerable purity comprising i) preparing a generator mixture comprising 227 Ac, 227 Th and 223 Ra; ii) loading said generator mixture onto a strong base anion exchange resin; iii) eluting said 223 Ra from said strong base anion exchange resin using a first mineral acid in an alcoholic aqueous solution to give a first eluted 223 Ra solution; iv) loading the 223 Ra of the first eluted 223 Ra solution onto a strong acid cation exchange resin; and v) eluting the 223 Ra from said strong acid cation exchange resin using a second mineral acid in aqueous solution to provide a second eluted solution. The invention additionally provides products of corresponding purity and/or products obtained or obtainable by such a method.
摘要:
Systems and methods are disclosed for producing customized, predictable, and reproducible supplies of radioisotopes using, for example, a reactor housing that is fabricated from a radioactive shielding material and has both an internal volume and a surface that comprises an entry port and an exit port, a chromatographic column that is positioned within said internal volume such that a first end of said column is in fluid communication with said entry port and a second end of said column is in fluid communication with said exit port, and a changeable filter module that is disposed external to said reactor housing and in fluid communication with said exit port.
摘要:
In a method and a device for producing a radionuclide, an absorption column containing the radionuclide is eluted by means of an eluent in a first flow direction and subsequently in a second, opposite flow direction.
摘要:
A column assembly of a radionuclide generator includes a column that retains a parent radionuclide that spontaneously decays to a relatively short-lived daughter radionuclide. A fluid path extends from an inlet port to the column and then to an outlet port and allows daughter radionuclide to be eluted from the radionuclide generator for use. Improved retention of parent radionuclide in the column is accomplished by preventing fluid from entering the flow path in a liquid state, such as during sterilization. Proper column chemistry is also promoted by preventing excess moisture from coalescing in the column, which may promote a higher and/or more reliable yield of daughter radionuclide from a radionuclide generator.
摘要:
At least one system (100) for eluting a radioactive material and a method of eluting a radioactive material is provided. The system for eluting a radioactive material may include an elution column (105) configured to enclose an radioactive material, a first sealing member sealing a first end of the elution column, a second sealing member sealing a second end of the elution column, an elution supply source (20) connected to the first end of the elution column via a first needle (22), a collection system (40) connected to the second end of the elution column via a second needle (42), and a filter (150) in the elution column, the filter being configured to support the radioactive material and prevent the radioactive material from contacting the second needle.