Black disazo dyes of general formula (V) wherein A is a moiety of formula (VI) or of formula (VII) and B is a moiety of formula (VII) or of formula (IX) and wherein M, R1, R2, R3, R4, R5, R6, R7, R8, R9, R10, R11, R12, R13, R14, R15, R16, R17, R18, R19, R20, R21, R22, R23, and R24, are as defined in the specification, are excellent black dyes for dying and printing cellulose containing materials and textile materials and, in particular, for preparation of recording liquids for ink jet printing and for writing utensils.

The present invention relates to a novel polymeric composition comprising a novel polymer having two or more repeat units and a terminus having the structure (1): wherein R1 represents a C1-C20 substituted or unsubstituted alkyl group, w is a number from 1-8, X is oxygen (O) or nitrogen (N), and Rd is a reactive group. The invention also relates to a process for forming a pattern using the novel polymeric composition. The invention further relates to a process of making the novel polymer.

Complexes of heterocyclic radionuclides are prepared based upon ligands having substituted pyridyl and imidazolyl groups. The ligands are bifunctional, having amino acid residues that may act as a linker to a bioactive molecu le, and a tridentate chelator that may complex the radionuclide. The bioactive molecule may be a peptide or somatostatin.

The present invention relates to lithium salt-containing rare earth halide solutions in aprotic solvents, processes for production thereof and also use thereof.

Methods and compositions for the deposition of a film on a substrate. In general, the disclosed compositions and methods utilize a precursor containing calcium or strontium.

Substrates for detecting microorganisms are provided, wherein the substrate comprises a set of molecular markers linked, optionally with linker molecules or moieties, to a di-, or tripeptide consisting of amino acids X1 and X2, or X1, X2 and X3, in which one of them, for example, X1, is a D-amino acid and the others, for example, X2 and X3, may be any D- or L-amino acid. The substrate preferably is used for the detection of Bacillus anthracis. Also provided are substrates for detecting Pseudomonas aeruginosa, wherein the substrate comprises a set of molecular markers linked, optionally with linker molecules or moieties to a tri-, tetra-, or pentapeptide consisting of glycine amino acids. The invention further comprises methods for detecting microorganisms, specifically B. anthracis and P. aeruginosa, with the substrates of the invention and use of the substrate(s) in such a method.

The invention relates to a bonding product suitable as a carrier for medicinal substances and to the compound derived therefrom that carries medicinal substances. The invention further relates to a process and device for preparing such bonding products and compounds. Further, the invention relates to a pharmaceutical composition containing such bonding products and compounds, and to the use thereof for preparing an infusible medicament for treating a disease.

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 coloring matter which exhibits excellent (ozone) gas resistance, high print density, low color rendering properties, low color saturation, and high-quality black hue when is recorded on a paper only for inkjet exclusive use, i.e., an azo compound represented by formula (1), a tautomer of the azo compound, or a salt of the azo compound or the tautomer; and an ink composition containing the coloring matter, particularly a black ink composition for inkjet recording applications.

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.

The purpose of the present invention is to provide novel liquid crystalline compounds that are capable of inducing phase transition by a light stimulus and are useful in the display, optoelectronics, and photonics field. The present invention relates to the liquid crystalline compounds represented by general formula (1): wherein R1, R2 and R3 are independently selected from the group consisting of hydrogen, alkyl, alkoxyl, alkoxycarbonyl, alkoxycarbonyloxy, alkanoyl, alkanoyloxy, alkoxyphenyl, and N-alkylaminocarbonyl, and n is an integer.

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.

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.

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.

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).

Described herein are pharmaceutical compositions and medicaments, and methods of using such pharmaceutical compositions and medicaments in the treatment of cancer.

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 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.

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.

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 for cooling a heat source, a method for preventing chemical interaction between a vessel and a cooling composition therein, and a cooling system. The method for cooling employs a containment vessel with an oxidizable interior wall. The interior wall is oxidized to form an oxide barrier layer thereon, the cooling composition is monitored for excess oxidizing agent, and a reducing agent is provided to eliminate excess oxidation. The method for preventing chemical interaction between a vessel and a cooling composition involves introducing a sufficient quantity of a reactant which is reactive with the vessel in order to produce a barrier layer therein that is non-reactive with the cooling composition. The cooling system includes a containment vessel with oxidizing agent and reducing agent delivery conveyances and a monitor of oxidation and reduction states so that proper maintenance of a vessel wall oxidation layer occurs.

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.

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 present invention relates to a liquid radioactive waste treatment system. The liquid radioactive waste treatment system includes a plurality of evaporation plates and each of the evaporation plates has an uneven surface, in a housing comprised of a glass. A liquid radioactive waste is dispersed via a liquid waste dispersing unit to the evaporation plate, and the liquid radioactive waste is evaporated using solar heat and airflow in the housing.

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.

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.

A reactor installation tool and method for installing a reactor unit in a reactor tube. A reactor installation tool including a movable assembly and a fixed assembly linked together such that the movable assembly can be adjusted relative to the fixed assembly. The movable assembly including a reactor sleeve attachment means for releasably securing a reactor sleeve loaded with a reactor unit to the tool. The fixed assembly including an expandable clamping unit for releasably securing the tool to a reactor tube. A reactor unit can be installed in the reactor tube by adjusting the movable assembly to extract the reactor unit from the reactor sleeve as the fixed assembly is rigidly secured to the reactor tube. The fixed assembly can be released from the reactor tube and the reactor installation tool can be removed from the reactor tube.

A method for recovery of residual actinide element from chloride molten salts that are formed after electro-refining and/or electro-winning of a spent nuclear fuel and include actinide elements and rare-earth elements is provided. The method comprises conducting electrolysis using a liquid cadmium cathode (LCC) in the chloride molten salt that is formed after electro-refining and/or electro-winning of a spent nuclear fuel and contains rare-earth elements and actinide elements; electro-depositing the actinide elements contained in the chloride molten salt on the LCC in order to reduce a concentration of the actinide elements; and adding a CdCl2 oxidant to the chloride molten salt containing the LCC-metal alloy in order to oxidize the rare-earth elements co-deposited on the LCC, thereby forming the rare-earth chlorides in the chloride molten salt.

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between −10 et −20 MPa are made from an alloy with a content of Sn between Sn=(=0.025σ−0.25)% and Sn=−0.05σ%: those components subjected to such a stress of between 0 et −10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05σ+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07σ+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%. A fuel assembly made according to the method.

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

An apparatus for treating a radioactive nitrate waste liquid includes: a denitrification tank (12) that accommodates active sludge which adsorbs or takes in a radioactive substance in a nitrate waste liquid (11) containing nitrate and the radioactive substance and in which an anaerobic microorganism that reduces the nitrate to nitrogen gas grows; a reaeration tank (14) that aerates and mixes a denitrification-treated liquid (24) treated in the denitrification tank (12) with the active sludge in which the aerobic microorganism grows; and a sludge dissolution tank (81) that dissolves redundant sludge (26A, 26B) discharged from the denitrification tank (12) and the reaeration tank (14). Acetic peracid (80) is supplied to the sludge dissolution tank (81) to dissolve redundant sludge, a sludge lysate is supplied to the denitrification tank (12) as a carbon source (22), and acetic acid is supplied to the denitrification tank (12).

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

A reactor installation tool and method for installing a reactor unit in a reactor tube. A reactor installation tool including a movable assembly and a fixed assembly linked together such that the movable assembly can be adjusted relative to the fixed assembly. The movable assembly including a reactor sleeve attachment means for releasably securing a reactor sleeve loaded with a reactor unit to the tool. The fixed assembly including an expandable clamping unit for releasably securing the tool to a reactor tube. A reactor unit can be installed in the reactor tube by adjusting the movable assembly to extract the reactor unit from the reactor sleeve as the fixed assembly is rigidly secured to the reactor tube. The fixed assembly can be released from the reactor tube and the reactor installation tool can be removed from the reactor tube.

A method for measuring the neutron flux in the core of a nuclear reactor, the method including several steps recurrently performed at instants separated by a period, the method comprising at each given instant the following steps: acquiring a total signal by a cobalt neutron detector placed inside the core of the reactor; assessing a calibration factor representative of the delayed component of the total signal due to the presence of cobalt 60 in the neutron detector; assessing a corrected signal representative of the neutron flux at the detector from the total signal and from the calibration factor; assessing a slope representative of the time-dependent change of the calibration factor between the preceding instant and the given instant; the calibration factor at the given instant being assessed as a function of the calibration factor assessed at the preceding instant, of the slope, and of the time period separating the given instant from the preceding instant.

Disclosed embodiments include methods of assembling a vented nuclear fission fuel module. Given by way of non-limiting example and not of limitation, an illustrative method of assembling a vented nuclear fission fuel module includes receiving a nuclear fission fuel element capable of generating a gaseous fission product. A valve body is coupled to the nuclear fission fuel element, and the valve body defines a plenum therein for receiving the gaseous fission product. A valve is disposed in communication with the plenum for controllably venting the gaseous fission product from the plenum. A flexible diaphragm is coupled to the valve for moving the valve. A cap is mounted on the valve, and a manipulator extendable to the cap for manipulating the cap is received.

Described herein is a composition useful for inducing expression of genes whose expression is under control of an inducible promoter sequence and methods for the compositions preparation and use.