Patent classifications
B01D59/30
METHOD FOR PRODUCING DEUTERIUM-DEPLETED WATER AND METHOD FOR PRODUCING DEUTERIUM-CONCENTRATED WATER
According to the present invention, water is separated into deuterium-depleted water and deuterium-concentrated water easily at low cost. Provided is a method for producing deuterium-depleted water by removing heavy water and semi-heavy water from water, the method including: supplying water vapor for a predetermined time period to an adsorbent material 11 obtained by adding to a carbon material one or more of metals belonging to Group 8 to Group 13 of the Periodic Table of Elements as additive metals and causing the water vapor to adsorb while passing through the adsorbent material 11; subsequently bringing protium gas into contact with the adsorbent material 11; and then desorbing and collecting the water vapor that has adsorbed to the adsorbent material 11.
SYSTEMS AND METHODS FOR SEPARATING ISOTOPES FROM A SAMPLE OF FISSION PRODUCTS
Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a series configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a parallel configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.
SYSTEMS AND METHODS FOR SEPARATING ISOTOPES FROM A SAMPLE OF FISSION PRODUCTS
Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes (e.g., Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a series configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned (e.g., using valves) to a parallel configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.
Process for producing 2,3-butanediol
A method of producing 2,3-butanediol includes subjecting a 2,3-butanediol culture liquid produced by microbial fermentation to nanofiltration membrane treatment and ion-exchange treatment (Step A), and then adding an alkaline substance and performing distillation (Step B).
Process for producing 2,3-butanediol
A method of producing 2,3-butanediol includes subjecting a 2,3-butanediol culture liquid produced by microbial fermentation to nanofiltration membrane treatment and ion-exchange treatment (Step A), and then adding an alkaline substance and performing distillation (Step B).
Method for producing thorium-226
Disclosed herein are embodiments of a method for producing thorium-226. The method comprises separating thorium-226 from uranium-230 to produce a solution of thorium-226 in a solvent, such as a chelating buffer, suitable for direct labeling by a chelate. The thorium-226 may be separated from the uranium-230 using extraction chromatography. The extraction may be repeated multiple times as additional thorium-226 is produced by uranium-230 decay.
Method for producing thorium-226
Disclosed herein are embodiments of a method for producing thorium-226. The method comprises separating thorium-226 from uranium-230 to produce a solution of thorium-226 in a solvent, such as a chelating buffer, suitable for direct labeling by a chelate. The thorium-226 may be separated from the uranium-230 using extraction chromatography. The extraction may be repeated multiple times as additional thorium-226 is produced by uranium-230 decay.
LOW-ENERGY ELECTROCHEMICAL SEPARATION OF ISOTOPES
The invention relates to isotope separation methods, and methods for separating isotopes with low energy consumption, demonstrated using hydrogen isotopes. Also described are methods for enriching or depleting the isotope present in the hydrogen gas/vapour feed e.g. for tritium removal, tritium enrichment and deuterium enrichment, by arranging a series of cells in a cascaded configuration.
LOW-ENERGY ELECTROCHEMICAL SEPARATION OF ISOTOPES
The invention relates to isotope separation methods, and methods for separating isotopes with low energy consumption, demonstrated using hydrogen isotopes. Also described are methods for enriching or depleting the isotope present in the hydrogen gas/vapour feed e.g. for tritium removal, tritium enrichment and deuterium enrichment, by arranging a series of cells in a cascaded configuration.
REMOVAL OF FREE-UNLABELED CATIONIC AND ANIONIC SOLUTION PHASE RADIONUCLIDES FROM RADIOPHARMACEUTICALS USING SOLID-PHASE EXTRACTION TECHNIQUES
The present invention relates to a process of removing free-unlabeled radionuclides from a radiopharmaceutical prior to administering the radiopharmaceutical to the patient using size-exclusion or ion-exchange mechanisms.