C01P2006/88

Purification of 68Ge/68Ga generator eluate from Fe(III) intended to improve specific radioactivity of 68Ga-based radiopharmaceuticals
09790097 · 2017-10-17 · ·

The present invention provides a method of purifying .sup.68Ge/.sup.68Ga generator produced .sup.68Ga from Fe (III). The invention further relates to an automated system within an existing Gallea Synthia prototype that provides purification .sup.68Ga from various cations and preconcentrations of .sup.68Ga. In general, the present invention further depicts the use of an automated system for the production of .sup.68Ga-radiolabelled PET tracers with high specific radioactivity and a kit for purifying .sup.68Ge/.sup.68Ga generator produced .sup.68Ga from Fe (III).

Isotopically-enriched boron-containing compounds, and methods of making and using same

An isotopically-enriched, boron-containing compound comprising two or more boron atoms and at least one fluorine atom, wherein at least one of the boron atoms contains a desired isotope of boron in a concentration or ratio greater than a natural abundance concentration or ratio thereof. The compound may have a chemical formula of B.sub.2F.sub.4. Synthesis methods for such compounds, and ion implantation methods using such compounds, are described, as well as storage and dispensing vessels in which the isotopically-enriched, boron-containing compound is advantageously contained for subsequent dispensing use.

Process to prepare surface-modified mineral material, resulting products and uses thereof

The present invention refers to a process to modify at least part of the surface of at least one mineral material, and to the use, as an additive in an aqueous suspension of mineral materials having a pH between 5 and 10, of at least one agent, wherein the additive allows for the formation of a low volume, high solids content filter or centrifuge cake on dewatering the suspension.

Purification of 68Ge/68Ga Generator Eluate From Fe(III) Intended To Improve Specific Radioactivity Of 68Ga-based Radiopharmaceuticals
20170029287 · 2017-02-02 ·

The present invention provides a method of purifying .sup.68Ge/.sup.68Ga generator produced .sup.68Ga from Fe (III). The invention further relates to an automated system within an existing Gallea Synthia prototype that provides purification .sup.68Ga from various cations and preconcentrations of .sup.68Ga. In general, the present invention further depicts the use of an automated system for the production of .sup.68Ga-radiolabelled PET tracers with high specific radioactivity and a kit for purifying .sup.68Ge/.sup.68Ga generator produced .sup.68Ga from Fe (III).

PROCESS TO PREPARE SURFACE-MODIFIED MINERAL MATERIAL, RESULTING PRODUCTS AND USES THEREOF

The present invention refers to a process to modify at least part of the surface of at least one mineral material, and to the use, as an additive in an aqueous suspension of mineral materials having a pH between 5 and 10, of at least one agent, wherein the additive allows for the formation of a low volume, high solids content filter or centrifuge cake on dewatering the suspension.

COPPER-64 COMPOSITIONS AND PURIFICATION PROCESSES FOR THE PREPARATION OF NOVEL COPPER-64 COMPOSITIONS

Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 110 Ci, about 15 Ci to about 110 Ci, or about 20 Ci to about 110 Ci of isolated copper-64 and have specific activities of about 50 mCi to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions may comprise bombarding a nickel-64 target with a low-medium energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography and/or a process comprising a combination of extraction chromatography and ion exchange chromatography.

ISOTOPIC SEPARATION OF LITHIUM
20250206609 · 2025-06-26 ·

The present disclosure relates to a method for isotopic separation of lithium, the method comprising:providing a first mixture (104) comprising at least lithium, lithium hydride, and possibly lithium deuteride and/or lithium tritide, the first mixture being at a first temperature;a first cooling step (110), preferably a uniform cooling, adapted to cooling the first mixture at a second temperature lower than the first temperature; the first cooling step being adapted to precipitating a first part of the lithium hydride having a first lithium isotope;a first separation step (124) adapted to separating the precipitated first part of the lithium hydride from the first mixture, forming a second mixture (122).

DEVICE AND METHOD FOR EXTRACTION OF LITHIUM HYDRIDES
20250214837 · 2025-07-03 ·

The present disclosure relates to a method for separating lithium from a lithium mixture, the method comprising: providing a first mixture (104) comprising lithium, lithium hydride, and at least a first compound among lithium deuteride and lithium tritide, the first mixture being at a first temperature: a first stirring step (108) adapted to stirring the first mixture: a first cooling step (110) adapted to cooling. preferably uniformly. the first mixture to a second temperature lower than the first temperature: the first stirring and cooling steps being adapted to deposit at least part of the first compound: and a first separation step (116) adapted to separating at least the deposited first compound from the first mixture. forming a second mixture (118) comprising at least lithium and lithium hydride.

SYSTEMS AND METHODS FOR GENERATING RADIONUCLIDES
20250368525 · 2025-12-04 ·

Systems and methods for generating radionuclides, such as radium-224. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228 and bismuth-212, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a third resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

COPPER-64 COMPOSITIONS AND PURIFICATION PROCESSES FOR THE PREPARATION OF NOVEL COPPER-64 COMPOSITIONS
20250368528 · 2025-12-04 ·

The present invention relates to novel compositions comprising high levels of copper-64 (e.g., high radionuclidic purity, high activity, and/or high specific activity), and processes for preparing said compositions. The compositions may comprise from about 2 Ci to about 120 Ci, about 15 Ci to about 120 Ci, about 20 Ci to about 120 Ci, about 30 Ci to about 120 Ci, about 40 Ci to about 110 Ci, or about 50 Ci to about 120 Ci of isolated copper-64 and/or have specific activities of about 10 mCi to about 3850 mCi copper-64 per microgram of copper. The processes for preparing said compositions may comprise bombarding a nickel-64 target with a low-medium energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography and/or a process comprising a combination of extraction chromatography and ion exchange chromatography.