Abstract: The present disclosure generally relates to a new process for generating germanium-68 from an irradiated target body. The process includes irradiation of the target body followed by various extraction techniques to generate the germanium-68.

Abstract: HEPA filter integrity testing apparatus including an automated mover, a scan module connected to the automated mover, and scan probes disposed along the length of the scan module. Assemblies also include HEPA filters and the filter integrity testing apparatus. A method of determining the integrity of HEPA filters with the filter integrity apparatus is disclosed.

Abstract: Systems and methods for dispensing radioactive liquids using a liquid dispensing apparatus are described. The apparatus includes a support arm rotatable about a rotation axis, an actuator operatively connected to the support arm and configured to at least one of rotate the support arm about the rotation axis and displace the support arm in a direction parallel to the rotation axis, and a pipette assembly mounted to the support arm. The pipette assembly includes a pipette tip defining an opening through which liquids are aspirated and dispensed, a piston, and a stepper motor operatively connected to the piston to control linear displacement of the piston.

Abstract: A system for manufacturing radionuclide generators includes an enclosure defining a radioactive environment. The enclosure includes radiation shielding to prevent radiation within the radioactive environment from moving to an exterior of the enclosure. The system also includes a conveyance system having a forward track and first carriages positioned on and movable along the forward track for conveying racks in a first direction. The conveyance system also includes a first walking beam mechanism magnetically coupled to the first carriages to move the first carriages. The conveyance system further includes a return track and second carriages positioned on and movable along the return track for conveying racks in a second direction opposite the first direction. The forward track and the return track form a loop.

Abstract: A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the acidic solution i), ii) or iii) having been treated to harvest Mo-99, wherein the process comprises contacting the treated acidic solution with an adsorbent comprising ammonium molybdophosphate (AMP). In an embodiment, the AMP is combined with an organic or inorganic polymeric support, for example AMP synthesized within hollow aluminosilicate microspheres (AMP-C).

Abstract: A process for purifying Mo-99 from an acidic solution obtained by dissolving an irradiated solid target comprising uranium in an acidic medium, or from an acidic solution comprising uranium and which has previously been irradiated in a nuclear reactor, or from an acidic solution comprising uranium and which has been used as reactor fuel in a homogeneous reactor, the process comprising contacting the acidic solution with an adsorbent comprising a zirconium oxide, zirconium hydroxide, zirconium alkoxide, zirconium halide and/or zirconium oxide halide, and eluting the Mo-99 from the adsorbent using a solution of a strong base, the eluate then being subjected to a subsequent purification process involving an alkaline-based Mo-99 chromatographic recovery step on an anion exchange material. Also provided is apparatus for carrying out the process.

Abstract: A system for assaying a sample for Molybdenum-99 content includes an inner ionization chamber including a well configured to receive the sample, an outer ionization chamber concentric with the inner ionization chamber, attenuating material positioned in the well, and a computing device. The computing device is configured to determine a first Molybdenum-99 content value of the sample based on a first current measured in the inner ionization chamber, determine a second Molybdenum-99 content value of the sample based on a second current measured in the outer ionization chamber, and determine a final Molybdenum-99 content value based on the first and second Molybdenum-99 content values.

Abstract: A horizontal mixer (50) is disclosed. Multiple blades (92) are affixed to and rotate with a tumbler (80) of the mixer (50). These blades (92) extend within an interior mixing chamber (90) and are center-angled so as to promote a desirable mixing action within this chamber (90) (e.g. so as to fold a slurry within the chamber (90) onto itself). One characterization is that the blades (92) are oriented so as to direct a flow toward a common outlet region (78) within the tumbler (80) throughout at least a certain rotational angle. The mixer (50) is particularly suited for realizing a desirable homogeneity of particles within a slurry from which radioisotopes may be produced.

Abstract: 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).