Abstract: Provided are methods for assessing T cell receptor ? chain complementary determining region 3 (TCR? CDR3) sequences. In certain embodiments, prior to the assessing, the subject has been identified as having, or is suspected of having, inflammatory bowel disease (IBD). According to some embodiments, at the time of the assessing, the subject has one or more non-specific symptoms consistent with Crohn's disease. Also provided are methods comprising administering a Crohn's disease therapy to a subject identified as comprising T cells that express a T cell receptor ? chain (TCR?) comprising a TCR? CDR3 sequence set forth in the present disclosure. Computer readable media and systems for assessing TCR? CDR3 sequences are also provided.

Abstract: The present invention is for processing fluids, especially waste streams from nuclear power plants, and other fluid media that may be carrying valuable or useful substances, in order to collect the substances. The system uses sequential filtering and multiple passes to concentrate the substances, which allows the system to collect virtually all of the substances of interest to the user while reducing the volume of both the unwanted materials as well as the desired materials desired without affecting the purity of the fluid after processing. Additionally, the collected substances can be processed in-place, and without requiring any thermal processing prior to disposal of unwanted substances, or for the recovery and/or reuse of valuable substances.

Abstract: The present invention is a system (or apparatus) and method for processing fluids, especially waste streams from nuclear power plants, and other fluid media that may be carrying valuable or useful substances, in order to collect the substances carried by such media. The system uses sequential filtering and multiple passes to concentrate the substances, which allows the system to collect virtually all of the substances of interest to the user while reducing the volume of both the unwanted materials as well as the desired materials desired without affecting the purity of the fluid after processing. Additionally, the collected substances can be processed in-place, and without requiring any thermal processing prior to disposal of unwanted substances, or for the recovery and/or reuse of valuable substances. Furthermore, the system provides other desirable features including, but not limited to, a novel multi-purpose container, and an optional means to stabilize waste through in-place solidification.

Abstract: An electrochemical leaching system for cleaning contaminated fines. The system has a waste vessel for receiving and holding a contaminated fines and lixiviant mixture. On a side of the waste vessel is an anolyte vessel holding an anolyte fluid. An anolyte barrier separates the waste and anolyte vessels. On an opposite side of the waste vessel is a catholyte vessel holding a catholyte fluid. A catholyte barrier separates the waste and catholyte vessels. A potential between an anode in the anolyte vessel and a cathode in the catholyte vessel ionizes the fines contaminants into anionic and cationic contaminants in the lixiviant. The anolyte and catholyte barriers allow the anionic and cationic contaminants, respectively, to flow from the lixiviant and into the anolyte and catholyte fluids in their respective vessels without allowing bulk transfer therebetween. The anionic and cationic contaminants are then removed from the anolyte and catholyte fluids. A cleaner lixiviant and fines exits the system.

Abstract: A method and system for improved ion exchange chromatographic elemental separations of zirconium and hafnium elements and also, if desired, separations of the isotopes thereof from crude zirconium minerals by using improved crude aqueous zirconium (also containing hafnium) chloride feedstock solutions, aqueous chloride eluant solutions, cationic or anionic exchange resins, and reduced ion exchange chromatographic operating temperatures. The method and system of the invention provides improved crude aqueous zirconium chloride feedstock solutions by carbochlorinating zircon sand and hydrolyzing and dissolving the chlorination products under controlled conditions to substantially eliminate cross-polymerization of the carbochlorination products, which undesirably yield inseparable zirconium and hafnium co-polymers during hydrolysis, by inhibiting the hydrolysis exotherm and/or the free acid generation during hydrolysis.

Abstract: The present invention provides methods and processes for immobilizing and solidifying harmful heavy metal and radioactive species within a waste material. The processes of the present invention are also particularly advantageous for immobilizing and solidifying nitrate compounds with a waste material. One embodiment of the present invention is a method that can be carried out by admixing the waste material with cement and a complexant compound to form a grout admixture. Preferably, the complexant compound is an iron compound that can form a hydrated iron oxide in the presence of an aqueous solution. This grout admixture is then allowed to cure and solidify. The grout admixture is placed within a suitable containment vessel for final storage and disposal.

Abstract: A method and system for improved continuous ion exchange chromatographic elemental separations of zirconium and hafnium and also for isotopic separations thereof from crude zirconium minerals by using zirconium (also containing hafnium) sulfate feedstock solutions, sulfate eluant solutions, anionic exchange resins, and reduced ion exchange column operating temperatures. The method and system of the invention provides sulfate feedstock solutions by completely converting the carbochlorination products of zircon sand to sulfate solutions prior to feeding to the ion exchange chromatographic column. The method and system of the invention is performed in a continuously operating continuous annular chromatograph (CAC). Nuclear grade substantially purified zirconium and hafnium metals are produced.

Abstract: A method and apparatus for the partial or complete continuous separation of isotopes of gadolinium, especially high thermal neutron capture cross-section gadolinium isotopes, using continuous, steady-state, chromatography in which an ion exchange resin is the stationary phase, an aqueous solution of ions based on a mixture of gadolinium isotopes is the feed phase, and an aqueous acid eluant solution is the mobile phase. The method involves the mobile phase eluting or desorbing the gadolinium isotopic solute or ligand adsorbed on the stationary phase under conditions such that each of the various naturally occurring isotopes of gadolinium is primarily eluted in an elution volume distinct from the elution volumes of the other isotopes. In a preferred embodiment, the conditions are such that at least one of the elution volumes contains essentially only one isotope of gadolinium.

Abstract: A novel method for decontaminating radio-contaminated nickel comprising, in an electrorefining cell having a semi-permeable membrane, cathodically depositing substantially contaminant-free nickel from an alkaline solution containing electrolyte, nickel ions, and radioactive ions. Preferably, the electrolyte solution is ammonium sulfate maintained at a pH of least about 10 (as measured at cell temperature). The electrorefining methods of the invention eliminate the need for separate dissolving and plating tanks, and may be operated by a single power source. These methods are particularly useful for remediating nickel contaminated by technetium, uranium and actinide metals.

Abstract: A process for the partial or complete simultaneous separation of isotopes of erbium, especially high thermal neutron capture cross-section erbium isotopes, using continuous, steady-state, chromatography in which an ion exchange resin is the stationary phase, an aqueous solution of ions based on a mixture of erbium isotopes is the feed phase, and an aqueous acid eluant solution is the mobile phase. The process involves the mobile phase eluting or desorbing the erbium isotopic solute adsorbed on the stationary phase under conditions such that each of the various naturally occurring isotopes of erbium is primarily eluted in an elution volume distinct from the elution volumes of the other isotopes. In a preferred embodiment, the conditions are such that at least one of the elution volumes contains essentially only one isotope of erbium. The process is preferably conducted in a continuous, steady-state manner, and in particular is preferably conducted in a continuous annular chromatograph (CAC).

Abstract: The present invention provides an improved multilayered storage structure composite material. The composite contains a fibrous mat made from interwoven fibers, preferably metallic fibers, that is encased with a concrete-based mixture to form a mat layer. At least one concrete-based layer is also disposed within the composite, and this concrete-based layer preferably contains at least one shielding additive. The composite material is preferably formed into a containment vessel for the storage of hazardous, radioactive, and mixed waste materials.

Abstract: Technetium-contaminated nickel is decontaminated by electrolytically dissolving nickel having a gross beta activity of at least about 74 Bq in a sulfuric acid solution having a pH between about 0.5 and 2.0. The applied voltage is from 2.0 v/cell to 5.0 v/cell for dissolving the nickel and contaminants while cathodically producing hydrogen gas. Technetium (+4) species in the acid solution is oxidized to the technetium (+7) species. The pH of the technetium-containing acid solution is adjusted to between 2.5 to 4.5. Particulates in the acid solution are filtered from the solution for reducing the gross beta activity of the acid solution to less than about 50 Bq/gm. Radioactive ions (including technetium complexes) are sorbed in an anionic exchanger and a cationic exchanger for reducing the gross beta activity of the acid solution to less than about 20 Bq/gm. After verifying the gross beta activity of the acid solution, the acid solution is either recycled or charged to a electrowinning step.

Abstract: Nickel (or other transition metal) contaminated with about 5 ppm technetium is decontaminated by dissolving the nickel and the technetium into an aqueous acid solution while introducing a graphite or activated carbon powder into the acid to immediately adsorb the dissolving technetium. The technetium-contaminated powder is separated from the aqueous acid solution and the nickel is then electrowon from the solution. The depleted acid solution is then recycled back to the dissolution step.

Abstract: An inorganic based strippable coating is provided for isolating hazardous materials. The coating is formed from a metal alkoxide material which undergoes a sol-gel reaction to form a metal oxide material. While the sol is still in a green state, the sol is applied to the surface to be protected. Any hazardous material such as nuclear contamination present on the surface is trapped within the matrix of the sol. The sol coating may be stripped from the surface while in a green state or may be allowed to harden. Once hardened, the sol forms a metal oxide coating which will deter the future accumulation of contamination.

Abstract: Technetium is separated from nickel by electro-refining contaminated nickel. Electrorefining controls the electrolyte solution oxidation potential to selectively reduce the technetium from the metallic feedstock solution from Tc(VII) to Tc(IV) forcing it to report to the anodic slimes and thereby preventing it from reporting to the cathodic metal product. This method eliminates the need for peripheral decontamination processes such as solvent extraction to remove the technetium prior to nickel electrorefining. These methods are particularly useful for remediating nickel contaminated by radio-contaminants such as technetium and actinides.

Abstract: The invention is both a system and method for continuously separating heavier from lighter isotopes of a particular element, such as zirconium. The system comprises a housing, a column assembly rotatably mounted with respect to the housing which includes a plurality of vertically oriented separation cells arranged in a circle, each of which contains a packing material, both a feed electrolyte source and a barren electrolyte source, each of which has an outlet mounted in the housing for continuously introducing either a feed electrolyte or a barren electrolyte into each of the cells as they rotate past the outlets, and upper and lower electrodes disposed over the upper and lower ends of the separation cells for inducing the electromigration of the lighter zirconium ions toward the lower ends of each of the separation cells. A drain assembly disposed beneath the column assembly continuously collects isotopic enriched electrolyte from the bottom ends of the separation cells.

Abstract: The thermal neutron capture cross-section of zirconium may be altered by altering its natural isotope distribution through a steady state chromatographic separation of these isotopes using an anion exchange resin as the stationary phase of the chromatographic column. Zirconium is dissolved in a very strong acid which causes the formation of a zirconium anion, such as the ZrOCl.sub.4.sup.-2 anion formed in six normal hydrochloric acid, and eluted off the column with a weaker acid. Distinct elution volumes representative of each isotope are collected. In a preferred embodiment, the process also separates the zirconium from hafnium and the other impurities normally present in the product obtained by chlorinating zircon sand and utilizes a continuous annular chromatograph.

Abstract: Two alternate, mutually exclusive, methods of removing radio contaminants from metal are taught based respectively on electrowinning or electrorefining of the base metal. The alternative using electrorefining controls the anolyte oxidation potential to selectively reduce the technetium in the metallic feedstock solution from Tc(VII) to Tc(IV) forcing it to report to the anodic slimes preventing it from reporting to the cathodic metal product. This method eliminates the need for peripheral decontamination processes such as solvent extraction and/or ion exchange to remove the technetium prior to nickel electrorefining. The other alternative method combines solvent extraction with electrowinning. By oxidizing technetium to the heptavalent state and by using mixtures of tri-n-octyalphosphine oxide and di-2-ethyl phosphoric acid in aliphatic hydrocarbon carriers to extract the radio contaminants prior to electrowinning, the background metal may be recovered for beneficial reuse.

Abstract: Electrical insulation which has good dielectric strength, good radiation resistance, and good thermal resistance at temperatures of up to 500.degree. C. and, preferably up to 1700.degree. C., includes a substrate which is flexible, has the form of a filament, sheet, wrapper, tape or sleeve, and consists essentially of inorganic materials selected from the group consisting of inorganic fibers and metals, metalloids, or alloys; and at least one layer of at least one oxide of an alkoxide-forming element provided on the substrate to impregnate and/or coat same. The insulation is prepared by a process including applying a solution containing an alkoxy gel polymer, optionally additionally containing at least one inorganic material in finely divided form, to the substrate to provide a treated substrate useful as a preform when allowed to set under ambient conditions.

Abstract: A simple, low temperature process for separating uranium isotopes and producing substantially pure uranium isotope fractions from a crude uranium isotope-containing aqueous feed stock is provided. A uranium isotope-containing solution is fed to an anion exchange resin in a continuously rotating annular chromatograph as a suitable eluant is also simultaneously fed to the rotating chromatograph. A Uranium 235, a Uranium 238 and an impurity fraction are recovered from the chromatograph. The substantially pure uranium 235 and uranium 238 fractions may be subjected to further processing, preferably precipitation with ammonium hydroxide to produce ammonium diuranate, and then calcining to form uranium oxide rich in the desired isotope.