A cycloalkyl triamine pentacarboxylate compound coordinating to a metal ion to form a high stability metal complex in serum is provided. The metal complex of the present invention can be used as a contrast agent for magnetic resonance imaging (MRI).

Novel radiopharmaceuticals that are useful in diagnostic imaging and therapeutic treatment of disease characterized by over expression of CA-IX comprise a complex that contains a sulfonamide moiety which is capable of binding the active catalytic site of CA-IX, and a radionuclide adapted for radioimaging and/or radiotherapy:

This invention relates to novel Ln(III) complexes of pybox, and methods of making the same. The present invention also relates to a method of use of pybox as a chelating moiety and sensitizer for Ln(III) ion luminescence. Derivatives of pybox and methods of making the same are also provided.

Disclosed is a spectrofluorimetrically detectable luminescent composition consisting essentially of at least one energy transfer acceptor lanthanide(III) complex having an emission spectrum maximum in the range from 300 to 2000 nanometers and a luminescence-enhancing amount of at least one energy transfer donor selected from the group consisting of a fluorophore, a lumiphore, an organic compound, a salt of an organic ion, a metal ion, a metal ion complex, or a combination thereof. Such energy transfer donor enhances the luminescence of at least one energy transfer acceptor lanthanide(III) complex, with the conditions that the emission spectrum of any energy transfer donor differs from that of its energy transfer acceptor lanthanide(III) complex; and such energy transfer donor can be dissolved to form a unitary solution in a solvent having an evaporation rate at least as great as that of water.

A light absorption anisotropic film, having at least one dichroic dye, in which the light absorption anisotropic film shows a diffraction peak derived from a periodic structure in a direction in a plane of the light absorption anisotropic film in X-ray diffraction measurement and the diffraction peak has a half width of 1.0 Å or less.

The new metal azo pigments comprising the adduct of a) at least two metal azo compounds of the formula (I) or their tautomeric forms in which the substituents have the definition indicated in the description,and b) at least one compound of the formula (II) in whichR6 has the definition indicated in the description, are characterized in that in the X-ray diffractogram with a lattice constant of d=10.3 (±0.2) Å the metal azo pigment has a signal S1 with an intensity I1 and in the lattice constant range from d=16.05 Å to d=11.78 Å has no signal S2 whose intensity I2 in relation to the intensity I1 of signal S1, expressed as ratio I2/I1 of the background-corrected intensities, exceeds a value of 0.02,and are outstandingly suitable for producing pigment preparations and especially for producing color filters.

It is an object of the present invention to provide antimicrobial metallodrugs comprising an antimicrobial peptide (“AMP”) and/or an antibiotic covalently bound to a metal binding moiety. These metallodrugs combine a metal binding domain which typically catalyzes oxido-reductase chemistry or acts as a Lewis-Acid catalyst, with a member of a diverse class of antimicrobial agents currently validated in preclinical and clinical settings for the treatment of a broad spectrum of pathogenic organisms.

Disclosed is a process for preparing a polyester or copolymer containing ester functionalities. The process can comprise: providing an optionally substituted lactone having a ring size of from 6 to 40 carbon atoms; andsubjecting said lactone to metal mediated ring-opening polymerization using as catalyst a compound according to general formula (I): wherein M can be Al, Cr, Mn and Co;X and X' are independently a heteroatom;Y and Y' can be, independently, selected from O, N, S, P, C, Si, and B;Z can be selected from hydrogen, borohydrides, aluminum hydrides, carbyls, silyls, hydroxide, alkoxides, aryloxides, carboxylates, carbonates, carbamates, amidos, thiolates, phosphides, and halides;L1 and L2 can be independently an organic ligand linking X and Y together and linking X' and Y' together, respectively; andL3 is an optional organic ligand linking Y and Y' together.

Disclosed is an azo compound represented by the formula (1) below, a salt thereof, or a copper complex salt compound thereof. (In the formula, R1 and R2 independently represent a hydrogen atom, a sulfonic acid group, a lower alkyl group or a lower alkoxyl group; R3-R6 independently represent a hydrogen atom, a lower alkyl group or a lower alkoxyl group; R7 represents a lower alkyl group or a lower alkoxyl group; and n represents 0 or 1.)

Chelators of the formulae (I), (II) and (III) and tricarbonyl complexes of radioisotopes of Tc and Re bound to them, for use in myocardial imaging.

A reagent for conjugation to a biomolecule, wherein the reagent is a single molecule with at least three functional parts and has schematic structure (I): a) wherein a trifunctional cross-linking moiety is coupled to b) an affinity ligand via a linker 1, said affinity ligand being capable of binding with another molecule having affinity for said ligand, to c) an effector agent, optionally via a linker 2, said effector agent exerting its effect on cells, tissues and/or humorous molecules in vivo or ex vivo, and to d) a biomolecule reactive moiety, optionally via a linker 3, said moiety being capable of forming a bond between the reagent and the biomolecule.

This invention relates to bis-azo colorants for use as bluing agents, laundry care compositions comprising bis-azo colorants that may serve as bluing agents, processes for making such bluing agents and laundry care compositions and methods of using the same. The bluing agents are generally comprised of at least two components: at least one chromophore component and at least one polymeric component. These bluing agents are advantageous in providing a whitening effect to fabrics, while not building up over time and causing undesirable blue discoloration to the treated fabrics.

The present invention relates to compounds suitable as modulators of protein misfolding and/or protein aggregation. The compounds are particularly suitable as inhibitors of amyloid aggregate formation and/or modulators of amyloid surface properties, and/or as activators of degradation or reduction of amyloid aggregates.

The rare-earth complex of the present invention has high luminous efficiency, since it has a structure represented by the following general formula (I):

Provided, amongst other things, are dyes of formula II: wherein R1, R2, R3 and R4 are independently H or alkyl, so long as one or more is alkyl, and salts of the compound of formula II. Methods of making, inks, surgical markers and methods of marking tissue and the like are further provided.

The present invention concerns a Ga68 complex of formula FOLATE-(LINKER)i-NOTA-Ga68 in which: 1) FOLATE is a folate compound or a derivative thereof capable of targeting a folate receptor,2) NOTA is a chelate capable of complexing Ga68 having a NOTA scaffold or derivatives thereof3) LINKER is a chemical group linking FOLATE and NOTA4) i is an integer chosen between 0 and 1 wherein NOTA is complexing Ga68.

Disclosed herein is a GO-Gd-DTPA (gadolinium-diethylenetriamine pentaacetic-graphene oxide) complex, which is formed by an ester bond of graphene oxide (GO) and gadopentetic acid (Gd-DTPA). Since the GO-Gd-DTPA can stably exist in the body because it has high stability in water, it is expected that it can be effectively used as an MRI contrast agent.

The present disclosure provides a photoreactive synthetic regulator of protein function. The present disclosure further provides a light-regulated polypeptide that includes a subject synthetic regulator. Also provided are cells and membranes comprising a subject light-regulated polypeptide. The present disclosure further provides methods of modulating protein function, involving use of light.

An organic compound has the following chemical structure: wherein R is different from R*; R and R* are independently hydrogen, halogen, nitro or methoxyl; and R1 is a C1-C6 alkyl or a phenyl group. A quaternary data storage device includes a bottom electrode, a top electrode, and the organic film layer sandwiched between the bottom electrode and the top electrode.

A liquid-crystal compound denoted by general formula (I) below wherein each of the groups is defined and Dye denotes an azo dye residue denoted by general formula (II) with X and n also being defined. The azo liquid-crystal compound is capable of orientation with a high degree of orientation order.

Porphyrin compounds are provided. The compounds may further comprise a fused polycyclic aromatic hydrocarbon or a fused heterocyclic aromatic. Fused polycyclic aromatic hydrocarbon s and fused heterocyclic aromatics may extend and broaden absorption, and modify the solubility, crystallinity, and film-forming properties of the porphyrin compounds. Additionally, devices comprising porphyrin compounds are also provided. The porphyrin compounds may be used in a donor/acceptor configuration with compounds, such as C60.

Provided is an oligonucleotide containing an azobenzene derivative, represented by Formula (1) or (2) below: (in the formulae, A1 and A2 each independently represent a hydrogen atom, nucleotide or oligonucleotide, B1 and B2 each independently represent a hydroxyl group, nucleotide or oligonucleotide, R11 and R12 each independently represent a C1-20 alkyl group, R21 and R22 each independently represent a hydrogen atom or C1-20 alkyl group, and R13 to R18 and R23 to R28 each independently represent a hydrogen atom; a C1-20 alkyl group or alkoxy group optionally substituted with a halogen atom, hydroxyl group, amino group, nitro group or carboxyl group; a C2-20 alkenyl group or alkynyl group optionally substituted with a halogen atom, hydroxyl group, amino group, nitro group or carboxyl group; a hydroxyl group; a halogen atom; an amino group; a nitro group; or a carboxyl group).

The present invention provides a family of dark quenchers, termed Black Hole Quenchers (“BHQs”), that are efficient quenchers of excited state energy but which are themselves substantially non-fluorescent. Also provided are methods of using the BHQs, probes incorporating the BHQs and methods of using the probes.

The present disclosure relates to an azoquinone compound represented by formula (1) below. In formula (1), R1 to R4 are identical or different and each represents a hydrogen atom, a C1 to C6 alkyl group or a C6 to C12 aryl group, and Ar represents a C6 to C12 aryl group.

A hypoxia contrast medium including nitroimidazole-amino acid chelate with a positively charged radioactive nuclide, a preparation method and use thereof. The contrast medium can be used in imaging cerebral thrombosis, tumors or other diseases such as ulceration, thrombosis, and so on.

The present invention relates to a method of differentially diagnosing different types of dementia. In particular, the method relates to the use of specific SPECT tracers for differentially diagnosing Alzheimer's disease, Lewy-Body Dementia, and Frontotemporal Dementia.

A method and apparatus for transporting syringes containing radioactive material. The apparatus includes a radiopharmaceutical pig having an inner chamber in which a sharps container can be secured. The sharps container has a housing and an attachable cap. The method includes assembling the radiopharmaceutical pig so that the chamber of the radiopharmaceutical pig contains the syringe in the sharps container housing. The radiopharmaceutical pig is disassembled, where upon the syringe is removed, discharged, and then replaced in the sharps container housing. The cap of the sharps container is affixed to the housing of the sharps container, thus enclosing the contaminated syringe therein. The radiopharmaceutical pig is assembled so that its chamber contains the sharps container and the syringe. The radiopharmaceutical pig is transported to a disposal area, where it is disassembled and the sharps container containing the syringe is placed in a particular disposal container.

A preferred embodiment may generally be construed as providing a method for storing fissile material, such as spent nuclear fuel (SNF), and includes the steps of: providing a storage container configured to receive the fissile material therein; and applying a coating to a surface of the storage container. Preferably, the coating is formed, at least in part, of a neutron-absorbing material and is adapted to reduce neutron multiplication and/or provide a shielding of the fissile material received within the storage container. Systems also are provided.

A spent fuel reprocessing method including the steps of partitioning U and Pu(III) in a solvent by solvent extraction and subsequently polishing the solvent in a neptunium rejection operation for removing Np therefrom. The solvent obtained from the neptunium rejection operation (the polished solvent or NpA solvent product) is then recycled to a U/Pu partitioning operation. The method enables a reduction in solvent feed and solvent effluent volumes.

The present invention relates to a process to dissolve plutonium or a plutonium alloy, by placing it in contact with an aqueous dissolution mixture, wherein said dissolution mixture comprises nitric acid, a carboxylic acid with complexing properties with respect to plutonium, and a compound comprising at least one —NH2 radical such as urea. The invention also relates to a process to convert plutonium or a plutonium alloy into plutonium oxide and to manufacture nuclear fuel from said oxide.The invention particularly applies to the dismantling of plutonium contained in nuclear weapons with a view to its use in civilian nuclear reactors, particularly in the form of MOX fuel.

This invention is provided for improvement of corrosion-resistant property of a crucible and for promotion of safety in a pyrochemical reprocessing method for the spent nuclear fuel. The spent nuclear fuel is dissolved in a molten salt placed in the crucible. In a pyrochemical reprocessing method, the nuclear fuel is deposited, and the crucible (2) is heated by induction heating. Cooling media (5, 6) are supplied to cool down, and a molten salt layer (7) is maintained by keeping balance between the heating and the cooling, and a solidified salt layer (8) is formed on inner wall surface of the crucible.

The invention provides a method of separating uranium from at least fission products in irradiated nuclear fuel, said method comprising reacting said irradiated nuclear fuel with a solution of ammonium fluoride in hydrogen fluoride fluorinating said reacted irradiated nuclear fuel to form a volatile uranium fluoride compound and separating said volatile uranium fluoride compound from involatile fission products. The invention thus provides a reprocessing scheme for irradiated nuclear fuel. The method is also capable of reacting, and breaking down Zircaloy cladding and stainless steel assembly components. Thus, whole fuel elements may be dissolved as one thereby simplifying procedures over conventional Purex processes.

In a chemical decontamination method of chemically decontaminating radioactive nuclides from a metallic material, oxalic acid and hydrazine are injected as a reductive decontaminating agent into water that is in contact with the metallic material. Injection of the hydrazine is stopped after a cation resin arranged in a circulation line connected to the metallic material breaks, and at least the oxalic acid and the hydrazine in the reductive decontaminating agent are decomposed using a decomposing catalyst.

A method and apparatus for transporting syringes containing radioactive material. The apparatus includes a radiopharmaceutical pig having an inner chamber in which a sharps container can be secured. The sharps container has a housing and an attachable cap. The method includes assembling the radiopharmaceutical pig so that the chamber of the radiopharmaceutical pig contains the syringe in the sharps container housing. The radiopharmaceutical pig is disassembled, where upon the syringe is removed, discharged, and then replaced in the sharps container housing. The cap of the sharps container is affixed to the housing of the sharps container, thus enclosing the contaminated syringe therein. The radiopharmaceutical pig is assembled so that its chamber contains the sharps container and the syringe. The radiopharmaceutical pig is transported to a disposal area, where it is disassembled and the sharps container containing the syringe is placed in a particular disposal container.

A method and apparatus for transporting syringes containing radioactive material. The apparatus includes a radiopharmaceutical pig having an inner chamber in which a sharps container can be secured. The sharps container has a housing and an attachable cap. The method includes assembling the radiopharmaceutical pig so that the chamber of the radiopharmaceutical pig contains the syringe in the sharps container housing. The radiopharmaceutical pig is disassembled, where upon the syringe is removed, discharged, and then replaced in the sharps container housing. The cap of the sharps container is affixed to the housing of the sharps container, thus enclosing the contaminated syringe therein. The radiopharmaceutical pig is assembled so that its chamber contains the sharps container and the syringe. The radiopharmaceutical pig is transported to a disposal area, where it is disassembled and the sharps container containing the syringe is placed in a particular disposal container.

A method for chemically decontaminating radioactive material. The method includes reducing-dissolving step for setting surface of radioactive material in contact with reducing decontamination liquid including mono-carboxylic acid and di-carboxylic acid as dissolvent; and oxidizing-dissolving step for setting the surface of the radioactive material in contact with oxidizing decontamination liquid including oxidizer. The method may include repeated pairs of steps, each pair including the reducing-dissolving step and the oxidizing-dissolving step. The mono-carboxylic acid may include formic acid, and the di-carboxylic acid includes oxalic acid. The oxidizer may be ozone, permanganic acid or permanganate.

A device for inspecting submersed plant parts is particularly suited for ultrasonic inspection of screws in the core baffle of a nuclear reactor pressure vessel. The device includes a remote-controlled underwater vehicle that is provided at its end face with a carrier that can be pivoted about a pivot axis oriented parallel to the longitudinal central axis of the underwater vehicle, and is provided with a holding device for an inspection head that is arranged on the carrier spaced apart from the pivot axis.

Decontamination of nuclear facilities is necessary to reduce the radiation field during normal operations and decommissioning of complex equipment. In this invention, we discuss gel and foam based diphosphonic acid (HEDPA) chemical solutions that are unique in that these solutions can be applied at room temperature; provide protection to the base metal for continued applications of the equipment; and reduce the final waste form production to one step. The HEDPA gels and foams are formulated with benign chemicals, including various solvents, such as ionic liquids and reducing and complexing agents such as hydroxamic acids, and formaldehyde sulfoxylate. Gel and foam based HEDPA processes allow for decontamination of difficult to reach surfaces that are unmanageable with traditional aqueous process methods. Also, the gel and foam components are optimized to maximize the dissolution rate and assist in the chemical transformation of the gel and foam to a stable waste form.

A variable-voltage variable-frequency power source for an electric motor that drives a re-circulation pump for a boiling water nuclear reactor. The power source has a semiconductor electric power converter and a speed controller for controlling the semiconductor electric power converter. When a part of the semiconductor electric power converter comes into an inoperative state, that part is electrically disconnected, and the variable-voltage variable-frequency power source temporarily stops outputting power, thereby idling the re-circulation pump. Thereafter, the power source re-starts outputting power before the re-circulation pump completely stops. Thus, the re-circulation pump keeps operating, without stopping.

Frames are disclosed for mounting windows within the walls of enclosures for isolating or sealing substances such as radioactive or other hazardous substances from the surrounding environment. In a first embodiment of the present invention, a window assembly includes a two-piece frame that is welded into the wall of an enclosure. In a second embodiment of the present invention, a window assembly includes a three-piece frame that is clamped to the wall of an enclosure. The frame assemblies may also be used to mount structures other than windows to enclosure walls, such as ducts or pipes intended for passing power, gas, vacuum, or other utilities into the interior of an enclosure.

A working apparatus has: a working equipment for doing works on a structure; an operation mechanism adapted to actively move the working equipment relative to the structure; and an adhering/traveling module coupled to the operation mechanism and adapted to adhere to the structure so as to have the weight of the working apparatus borne by the structure and travel/move on the structure for positioning. With this arrangement, the working apparatus can perform accurate positioning operations in a narrow environment and complex scanning operations by means of various pieces of the working equipment such as inspection sensors, and can secure a large working area within a short period of time and reduce the overall working hours.

A vol-oxidizer of spent nuclear fuel, the spent nuclear fuel is injected to a reaction portion, the reaction portion is connected to a driving portion and oxidizes the spent nuclear fuel by rotating and back-rotating the spent nuclear fuel. The oxidized powder of the spent nuclear fuel is gathered in a discharge portion located in a lower portion of the reaction portion. By providing minute powder particles for recycling and a post process of the spent nuclear fuel, even though a size of an apparatus is small, processing a large amount is possible. Time required for oxidation can be reduced, and the powder is readily discharged by gravity since the apparatus is vertically configured.

Disclosed is a separation and receiving apparatus for a spent nuclear fuel rod. The spent nuclear fuel rod is mounted and downwardly transferred by a pin. At this time, a blade peels the hull of the spent nuclear fuel rod. The hull and a pellet positioned therein are separated by a separator. The peeled hull and pellet are each received in respective receiving vessels. Accordingly, since the hull and pellet made of uranium oxide (UO2) may be automatically separated and received in each respective vessel, safety and automation may be guaranteed.

The flexible glove holder (1) includes a flat structure (13) with three branches (2, 3 and 4) forming an S-shape on which the glove is wound. The holder (1) is then pushed into the opening of the glove box. This rapid action method makes it possible to avoid knotting the gloves when they must be drawn toward the outside for an operation within the box and also allows the implementation of biological protection on the opening of the glove box as well as a protection of the agents against radiation.

Materials and methods of making low-sintering-temperature glass waste forms that sequester radioactive iodine in a strong and durable structure. First, the iodine is captured by an adsorbant, which forms an iodine-loaded material, e.g., AgI, AgI-zeolite, AgI-mordenite, Ag-silica aerogel, ZnI2, CuI, or Bi5O7I. Next, particles of the iodine-loaded material are mixed with powdered frits of low-sintering-temperature glasses (comprising various oxides of Si, B, Bi, Pb, and Zn), and then sintered at a relatively low temperature, ranging from 425° C. to 550° C. The sintering converts the mixed powders into a solid block of a glassy waste form, having low iodine leaching rates. The vitrified glassy waste form can contain as much as 60 wt % AgI. A preferred glass, having a sintering temperature of 500° C. (below the silver iodide sublimation temperature of 500° C.) was identified that contains oxides of boron, bismuth, and zinc, while containing essentially no lead or silicon.

Frames for mounting windows within the walls of enclosures for isolating or sealing substances such as radioactive or other hazardous substances from the surrounding environment. In a first embodiment of the present invention, a window assembly includes a two-piece frame that is welded into the wall of an enclosure. In a second embodiment of the present invention, a window assembly includes a three-piece frame that is clamped to the wall of an enclosure. The frame assemblies may also be used to mount structures other than windows to enclosure walls, such as ducts or pipes intended for passing power, gas, vacuum, or other utilities into the interior of an enclosure.

A system and method for a self-charging battery cell are provided in which beta emissions from a Strontium-90 source are obtained by a sensor device and converted into electric energy. In embodiments, a scintillation device is used to intake emissions from a Strontium-90 source, and consequently emit a light or plurality of light flashes. A sensor device, e.g., a photodiode, is utilized to convert the light or plurality of light flashes into electric voltage, current and/or energy.

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

A method of repairing a nuclear fuel cell wall and tools useful for performing that repair are described. A repair tool may be used to align a jack near a region of a bent or distorted structural component of nuclear fuel cell and that jack may be used to apply a force to that structural component. Application of such a force may serve to bend the structural component of a nuclear fuel cell in a way to restore the structural component to its position before damage occurred. The repair tool includes a way of mounting that tool to a fuel cell, positioning elements to align the tool near a structural deformation or bent element and a jack that may be use to apply a force to at least one structural component in a fuel cell.

Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.