An elution generator including an elution column having a container defining an interior volume and a septum, a radiation shield having an upper shield portion defining a central recess and a coaxial flow needle extending downwardly into the central recess, and a lower shield portion having body portion defining a central recess, wherein the elution column is disposed in the central recess of the lower shield portion, the body portion of the lower shield portion is disposed in the central recess of the upper shield portion, and the coaxial flow needle extends downwardly through the septum into the internal volume of the elution column.

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 fuel bundle surrogate for the irradiation of a target material, having a plurality of tube sheaths, each tube sheath being parallel to a longitudinal center axis of the fuel bundle surrogate, a plurality of end caps, a pair of end plates, wherein the end plates are disposed at opposing ends of the plurality of tube sheaths, and a first target comprised of a first target material suitable for producing the isotope by way of a neutron capture event, wherein the first target is disposed in a first tube sheath, and wherein the first tube sheath of the plurality of tube sheaths comprises an elongated thickened wall portion and a pair of annular end portions, each annular end portion being disposed on a corresponding end of the thickened wall portion and having a wall thickness that is less than a wall thickness of the thickened wall portion.

Disclosed is a method of producing Tc-99m by using nuclear resonance fluorescence. More specifically, and a method of preparing Tc-99m by using nuclear resonance fluorescence includes irradiating a ground-state Tc-99 nucleus with a photon beam, thereby causing a nuclear transmutation to proceed such that the nucleus excited to high energy and then undergoes a transition to Tc-99m.

A radioisotope production apparatus (RI) comprising an electron source arranged to provide an electron beam (E). The electron source comprises an electron injector (10) and an electron accelerator (20). The radioisotope production apparatus (RI) further comprises a target support structure configured to hold a target (30) and a beam splitter (40) arranged to direct the a first portion of the electron beam along a first path towards a first side of the target (30) and to direct a second portion of the electron beam along a second path towards a second side of the target (30).

The method and kit for detecting technetium-99m radioisotopes provide color-change solutions for visual detection of technetium-99m radioisotope-based tracers. A first color-change solution is formed from a mixture of thymol blue sodium salt solution and bromocresol purple solution. A first sample to be tested is determined to be a substance containing technetium-99m radioisotopes when the first sample to be tested turns yellow in color following spraying with the first color-change solution. A second color-change solution is formed from a mixture of bromocresol green solution and neutral red solution. A second sample to be tested is determined to be a substance containing technetium-99m radioisotopes when the second sample to be tested turns purple in color following spraying with the second color-change solution. The method and kit provide a rapid test for distinguishing a spill of radioactive TC-99m tracer from a saline spill in a nuclear medicine facility.

A system for converting an electron beam into a photon beam includes an electron accelerator configured for generating an electron beam of accelerated electrons along an irradiation axis (Z); a scanning unit; a focusing unit for forming a focused beam converging towards a first focusing point (Fx) located on the irradiation axis (Z); a converting unit located between the focusing unit and the first focusing point (Fx), and comprising one or more bremsstrahlung converters, configured for converting the focused beam into a photon beam, wherein the one or more bremsstrahlung converters are curved such that the focused beam intersects each of the one or more bremsstrahlung converters with an intersecting angle comprised between 65° and 115° at all points, preferably between 75° and 105° at all points; and a target holder configured for holding a target.

An irradiation target for the production of radioisotopes, having at least one plate defining a central opening, and a first elongated central member passing through the central opening of the at least one plate so that the at least one plate is retained thereon, wherein the at least one plate and the first elongated central member are both formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.

A fuel bundle surrogate for the irradiation of a target material, having a plurality of tube sheaths, each tube sheath being parallel to a longitudinal center axis of the fuel bundle surrogate, a plurality of end caps, a pair of end plates, wherein the end plates are disposed at opposing ends of the plurality of tube sheaths, and a first target comprised of a first target material suitable for producing the isotope by way of a neutron capture event, wherein the first target is disposed in a first tube sheath, and wherein the first tube sheath of the plurality of tube sheaths comprises an elongated thickened wall portion and a pair of annular end portions, each annular end portion being disposed on a corresponding end of the thickened wall portion and having a wall thickness that is less than a wall thickness of the thickened wall portion.

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.