A target irradiation system including an irradiated target removal system having a body defining a central bore, an elevator received within the central bore, and a docking surface for placing the irradiated target removal system in fluid communication with a vessel penetration of a reactor. A target canister slidably receives the radioisotope target therein, and the elevator is configured to receive the target canister. The elevator is lowered into the reactor when irradiating the radioisotope target, and the irradiated target removal system forms a portion of a pressure boundary of the reactor during target irradiation.

Disclosed is a calibrator device designed to measure the activity of a radio element, including: an ionization chamber, intended to receive the radio element; and electronic/computer system for controlling the operation of the calibrator device. The electronic/computer system includes voice control, which include: at least one microphone capable of capturing a voice instruction emitted by the operator; a recognition module designed to convert the voice instruction into a request that can be executed by the electronic/computer system; and a control module designed to control the execution of the request by the electronic/computer system.

An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.

A method of treating an adsorbent for a chromatographic separation. The method involves sonicating particles of an inorganic metal oxide having fragile edges in the absence of any alkylating or acylating agent to form smoothened particles of the inorganic metal oxide and washing the smoothened particles of the inorganic metal oxide to remove fine particulate matter to produce a treated adsorbent. The treated adsorbent can be used in a method of isolating a daughter radioisotope from a daughter radioisotope that is produced from the parent radioisotope by radioactive decay.

A process for producing a hardened target plate coated with a molybdenum-100 metal, comprising the steps of: (i) suspending and intermixing a refined molybdenum-100 metal powder having grain sizes of less than about 10 microns, and a binder, in a polar organic solvent; (ii) inserting into the molybdate-100 mixture, a cathode plate comprising a transition metal and an anode plate comprising conductive metal; (iii) applying a potential from about 300 V to about 1,300 V to the anode plate and cathode plate; (iv) recovering the cathode plate from the molybdate-100 mixture; and (v) sintering the cathode plate at a temperature from a range of about 1,200 C. to about 1,900 C. for a period of time from about 3 h to about 8 h.

A method includes sterilizing a column assembly including a column having a parent radionuclide contained therein with a sterilizer. The method further includes transferring the column assembly from the sterilizer to a first clean room environment, transferring the column assembly from the first clean room environment to a second clean room environment, and collecting a sterility test sample from the column assembly within the second clean room environment.

An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.

Accelerator based systems are disclosed for the generation of isotopes, such as molybdenum-98 (99Mo) and metastable technetium-99 (99mTc) from molybdenum-98 (98Mo). Multilayer targets are disclosed for use in the system and other systems to generate 99mTc and 98Mo, and other isotopes. In one example a multilayer target comprises a first, inner target of 98Mo surrounded, at least in part, by a separate, second outer layer of 98Mo. In another example, a first target layer of molybdenum-100 is surrounded, at least in part, by a second target layer of 98Mo. In another example, a first inner target comprises a Bremsstrahlung target material surrounded, at least in part, by a second target layer of molybdenum-100, surrounded, at least in part, by a third target layer of 98Mo.

A method for enhancing radionuclide activity of a daughter radionuclide-containing eluate obtained from a mixture of mother/daughter radionuclides is disclosed. This method comprises i) contacting separation particles with an aqueous solution containing a mixture of mother and daughter radionuclides wherein daughter radionuclides bind to separation particles and mother radionuclides does not. That contact is maintained ii) for a time for unbound daughter radionuclide to bind to the separation particles. Unbound mother radionuclide is iii) separated from the daughter radionuclide-bound separation particles using a washing solution. Steps i) and ii) are repeated at least once iv). The bound daughter radionuclide is stripped v) from the separation particles using a volume of stripping solution less than that used if only steps i), ii), iii) and v) were used for each of the recited at least two separations to form an aqueous eluate having enhanced daughter radionuclide activity.

A method for separating a parent isotope from a daughter isotope is provided, the method comprising supplying irradiated target; dissolving the irradiated target; treating the dissolved irradiated target to a precipitation step to form a first solid phase of the parent isotope and a first liquid phase of the daughter isotope; filtering the first liquid phase of daughter isotope to create a first purified fraction of the daughter isotope to create a second solid phase of the parent isotope and a second liquid phase of the daughter isotope; and filtering the second liquid phase to create a second liquid fraction of the daughter isotope. The process can be repeated until the .sup.99Mo is exhausted and the enriched target material .sup.98Mo or .sup.100Mo can be easily re-used.