An irradiation target system having an irradiation target with at least one annular plate defining a central opening and including an elongated body, a flange portion, and a tab portion, wherein the flange portion extends beyond a first end of the plurality of plates, a target debundling tool, having a base plate, a gripper assembly affixed to the base plate, and a twister assembly including a housing defining a target bore configured to receive the target therein, and a slide portion that is slidably and non-rotatably mounted to the housing at a bottom end of the target bore.

A system for producing technetium-99m from molybdate-100. The system comprises: a target capsule apparatus for housing a Mo-100-coated target plate; a target capsule pickup apparatus for engaging, and delivering the target cell apparatus into a target station apparatus; target station apparatus for receiving and mounting therein the target capsule apparatus. The target station apparatus is engaged with a cyclotron for irradiating the Mo-100-coated target plate with protons. The irradiated target capsule apparatus is transferred to a receiving cell apparatus comprising a dissolution/purification module for receiving therein a proton-irradiated Mo-100-coated target plate. A conveyance conduit infrastructure interconnects: (i) the target capsule pickup apparatus with the target station apparatus, (ii) the target station apparatus and the receiving cell apparatus; and (iii) the receiving cell apparatus and the dissolution/purification module.

A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.

Apparatuses and methods for production of molybdenum targets, and the formed molybdenum targets, used to produce Tc-99m are described. The target includes a copper support plate having a front face and a back face. The copper support plate desirably has dimensions of thickness of about 2.8 mm, a length of about 65 mm and a width of about 30 mm; and the copper support plate desirably has either a circular or an elliptical cavity centrally formed therein by pressing molybdenum powder into the front face with a depth of about 200-400 microns. Also, the copper support plate includes cooling channels dispensed at the back face; wherein the copper support plate is water cooled by a flow of water during irradiation by a proton beam. Molybdenum powder is embedded and compressed onto the cavity of the copper support plate thereby creating a thin layer of molybdenum onto the copper support plate.

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 system for producing technetium-99m from molybdate-100. The system comprises: a target capsule apparatus for housing a Mo-100-coated target plate; a target capsule pickup apparatus for engaging and delivering the target cell apparatus into a target station apparatus; a target station apparatus for receiving and mounting therein the target capsule apparatus. The target station apparatus is engaged with a cyclotron for irradiating the Mo-100-coated target plate with protons. The irradiated target capsule apparatus is transferred to a receiving cell apparatus comprising a dissolution/purification module for receiving therein a proton-irradiated Mo-100-coated target plate. A conveyance conduit infrastructure interconnects: (i) the target capsule pickup apparatus with the target station apparatus, (ii) the target station apparatus and the receiving cell apparatus; and (iii) the receiving cell apparatus and the dissolution/purification module.

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 initial introduction control part introduces an aqueous solution containing molybdenum 99 and technetium 99m, and an organic solvent being capable of dissolving the technetium 99m into an extraction tank. A micro-mixing control part micro-mixes the aqueous solution and the organic solvent by heating and stirring a mixed solution of the aqueous solution and the organic solvent introduced into the extraction tank with a heater, while applying ultrasonic to the mixed solution. A separation control part separates the mixed solution micro-mixed into two phases of aqueous solution and an organic solvent. A taking-out introduction control part passes the organic solvent separated into two phases through an adsorption column be capable of adsorbing molybdenum 99 and introduces the organic solvent into an evaporation elution tank. An evaporation control part evaporates the organic solvent and leaves residue by reducing pressure inside the evaporation elution tank and heating the organic solvent introduced into the evaporation elution tank with a heater, while applying ultrasonic to the organic solvent. An elution control part introduces physiological saline solution into the residue and elutes technetium 99m into the physiological saline solution from the residue.

A nuclear fuel, the nuclear fuel comprising uranium aluminide grains, wherein the uranium aluminide grain properties are selected for good isotope extraction after irradiation and chemical digestion.

A radioisotope production apparatus comprising an electron source arranged to provide an electron beam. The electron source comprises an electron injector and an electron accelerator. The radioisotope production apparatus further comprises a target support structure configured to hold a target and a beam splitter arranged to direct the a first portion of the electron beam along a first path towards a first side of the target and to direct a second portion of the electron beam along a second path towards a second side of the target.