G21G2001/0036

TARGET IRRADIATION SYSTEMS FOR THE PRODUCTION OF RADIOISOTOPES

A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, including a target delivery assembly including a body defining a central bore, a basket that is slidably receivable within the central bore of the body, and a winch that is connected to the basket by a cable, the target delivery assembly being affixed to the vessel penetration of the reactor, and a target passage that is in fluid communication with the target delivery assembly, wherein the basket is configured to receive the radioisotope target therein via the target passage and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target, and the target delivery system forms a portion of the pressure boundary of the reactor when in fluid communication with the reactor.

Target irradiation systems for the production of radioisotopes

A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, includes a target delivery assembly with a body defining a central bore, a basket that is slidably receivable within the central bore of the body, and a winch that is connected to the basket by a cable. The target delivery assembly is affixed to the vessel penetration of the reactor; and a target passage is in fluid communication with the target delivery assembly. The basket is configured to receive a radioisotope target therein via the target passage and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target. The target delivery system forms a portion of the pressure boundary of the reactor when in fluid communication with the reactor.

Production of Lu-177 and other radionuclides via hot atom capture on nanostructured carbon

Described are methods for preparing radionuclides, such as radionuclides having a high specific activity. The disclosed methods include irradiating target nuclide materials, in solution, with a neutron source. The radionuclides can be separated from the target nuclide material by providing a solid carbon nanostructured material, as a suspension of solids, proximal to the target nuclide material in solution and using the recoil to drive adsorption of the radionuclide onto the solid carbon nanostructured material to transfer the radionuclides from the liquid phase (in solution) to the solid phase (adsorbed to the suspended solid carbon nanostructured material). One or more surfactants can be incorporated into the solution to facilitate formation of a stable suspension of the solid carbon nanostructured material.

IRRADIATION TARGETS FOR THE PRODUCTION OF RADIOISOTOPES AND DEBUNDLING TOOL FOR DISASSEMBLY THEREOF
20220406482 · 2022-12-22 ·

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.

FUEL CHANNEL ISOTOPE IRRADIATION AT FULL OPERATING POWER
20220293291 · 2022-09-15 ·

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.

Target irradiation systems for the production of radioisotopes

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.

Chromatographic separation of Mo-99 from W-187
11380453 · 2022-07-05 · ·

The present disclosure provides a method of separating Mo-99 from W-187 from a solution comprising Mo-99 and W-187. The method comprises contacting a tridentate diglycolanude ligand with a solution comprising Mo-99 and W-187 and eluting W-187 from the tridentate diglycolanude ligand to thereby an eluate comprising W-187.

NOVEL METHOD TO SEPARATE ISOTOPES CREATED BY PHOTONUCLEAR REACTIONS
20220108813 · 2022-04-07 · ·

The widespread utilization and growing demand for radiopharmaceuticals are attributable to the development and availability of a range of radiopharmaceuticals. The present disclosure describes methods of making 3-dimensional nano-porous, micro-porous, meso-porous, or macro-porous materials. The present disclosure also describes methods of irradiating and separating isotopes using the 3-dimensional nano-porous, micro-porous, meso-porous, or macro-porous materials.

Surrogate isotope-containing materials for emergency response training and Methods of formation and dispersal

Surrogate materials are in the form of solid particles that include surrogate isotopes, namely, short-lived isotopes selected and formed to serve as surrogates for the radioactive materials of a nuclear fallout without including isotopes that are, or that decay to, biologically or environmentally deleterious and persistent isotopes. The surrogate material may be formed using high-purity reactant material and irradiation and separation techniques that enable tailoring of the isotopes and ratios thereof included in the surrogate material, and the surrogate material may be dispersed, e.g., in a training environment, in solid form.

Target irradiation systems for the production of radioisotopes

A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, including a target elevator assembly including a body portion defining a central bore and an open bottom end, a center tube that is disposed within the central bore of the body portion, a target basket that is slidably receivable within the center tube, and a winch that is connected to the target basket by a cable, wherein the target basket is configured to receive the radioisotope target therein and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target.