The present invention relates to an (amide amino alkane) metal compound represented by the formula (1): wherein M represents a metal atom;R1 represents a linear, branched or cyclic alkyl group having 1 to 6 carbon atoms;R2 and R3 may be the same as, or different from each other, and each independently represents a linear or branched alkyl group having 1 to 3 carbon atoms, or R2 and R3 may form a substituted or unsubstituted 5- or 6-membered ring together with the nitrogen atom to which they are bound;Z represents a linear or branched alkylene group having 1 to 10 carbon atoms (a part of which may optionally form a ring); andn represents a number of the ligands, which is equal to the valence of the metal (M), and represents an integer of from 1 to 3; with the proviso that the metal compounds in which M is Li (Lithium), Be (Beryllium), Ge (Germanium) or Nd (Neodymium) are excluded;the metal compounds in which M is Mg (Magnesium) and R1 is methyl group are excluded;the metal compounds in which M is Zn (Zinc) and R1 is methyl group are excluded;the metal compounds in which M is Bi (Bismuth) and R1 is t-butyl group are excluded; andin cases where n is two or greater, two or more ligands may be the same as, or different from each other; and a method of producing a metal-containing thin film using the metal compound.

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.

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.

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.

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.

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.

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.

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.

The present invention is directed to novel organometallic complexes as catalysts for the reaction of compounds with isocyanate and hydroxyl functional groups to form urethane and/or polyurethane and the process employing such catalysts. More particularly, the present invention is directed to novel complexes of zinc(II) with substituted amidines. These novel catalysts are useful for the production of urethanes and polyurethanes which are important in many industrial applications.

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.

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.

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 removing radioactive contaminants from a given surface. An acidic solution having a pH of less than 3.0, and preferably less than 1.5, of a complex substituted keto-amine, and a mixture of a saturated and unsaturated lower alcohol (e.g. isopropyl alcohol and propargyl alcohol), and concentrated acid is applied to a contaminated surface. The solution is left on said surface for a time sufficient to remove the radioactive contaminants into the acidic solution and then removed. The acidic solution containing the radioactive contaminants is preferably neuralized by an alkaline material to a pH of between 5.5 and 9.0. Removal of thorium contamination from railcars is one useful application of the invention. The method of the present invention has the effect of removing substantially all of the radioactive contaminants from a previously contaminated surface.

An apparatus and method for transporting radiopharmaceutical substances. The apparatus comprises a radiation shielding pig having an elongated sidewall that extends between two ends and that defines an elongated, interior chamber. The sidewall is thinner than each of the ends. A radiation shield defines at least one cavity. The shield has two open ends and a central area between the open ends that is thicker than each of the two open ends. Also, a method of assembling and disassembling the apparatus includes, placing a syringe filled with a radiopharmaceutical substance into the pig; placing the pig containing the filled syringe in the radiation shield; placing the pig and the shield into an ammunition can for transporting the radioactive substance contained in the syringe.

A method for removing radioactive contaminants from a given surface. An aqueous solution having a wetting agent and a complex substituted keto-amine is provided. The solution is left on the surface for a time sufficient to remove the radioactive contaminants into the aqueous solution which is then removed. Depending on the type and condition of the surface, a concentrated acid may be added to the aqueous solution to aid in the contaminant removal process. In such a case, a pH of less than 3.0, and preferably less than 1.5 is maintained. If a concentrated acid is used, the acidic solution containing radioactive contaminants is preferably neutralized by an alkaline material to a pH of between 5.5 and 9.0. Removal of thorium contamination from railcars is one useful application of the invention. The method of the present invention has the effect of removing substantially all of the radioactive contaminants from a previously contaminated surface.

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.

A method for removing a wide variety of radioactive contaminants from a contaminated surface sufficient for the surface to be classified as a low-level waste or as free release. Contaminated surfaces may be classified as Class C, Class B, Class A, or high-level radioactive wastes prior to treatment. An aqueous solution having a wetting agent and a complex substituted keto-amine is provided. The aqueous solution is left on the surface for a time sufficient to remove the radioactive contaminants into the aqueous solution which is then removed. Depending on the type and condition of the surface, an acid may be added to the aqueous solution to aid in the contaminant removal process. However, typical metals surfaces may often be treated effectively without the use of concentrated acids or with dilute concentrations of such acids. The method of the present invention has the effect of removing substantially all of the radioactive contaminants from a variety of previously contaminated surfaces.

The present invention concerns a process for dissolving ruthenium deposits that are present on a surface and a process for decontaminating the internal circuits of nuclear fuel reprocessing plants using the said dissolution process. The process according to the invention comprises bringing the said surface into contact with an aqueous solution of perruthenate, with the said aqueous solution having a pH equal to or greater than 12, so that the ruthenium is oxidised.

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.

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.

A radioactive substance decontamination method and apparatus which decontaminates a metal member contaminated by radioactive substance in a short period of time. This apparatus has (1) multiple reducing decontamination tanks having different radiation control values; (2) a carrier for immersing the metal member into the multiple reducing decontamination tanks and a washing tank; (3) a tube for transferring into the second reducing decontamination tank the reducing decontamination agent in the first reducing decontamination tank; (4) a reducing agent decomposer for decomposing a component contained in the reducing decontamination agent of the reducing decontamination tank where the radiation control value is the highest out of the reducing decontamination tanks connected by the tube; and (5) a washing tank for washing the reducing decontamination agent deposited on the decontaminated metal member.

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.

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.

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.

One form of the invention is directed to an apparatus that comprises step-down circuitry to better match impedance between an input and an output that includes a number of stages each electrically coupled to another and each including a charge storage device. The circuitry further includes a number of switching devices operable in a first electrical connectivity state to connect the charge storage device of each of the stages in series to receive electrical charge from the input and in a second electrical connectivity state opposite the first state to connect the charge storage device of each of the stages in parallel to discharge electricity through the output. This circuitry can be used in connection with a radioisotopic conversion cell.

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.

A hydrogen combustion system comprising: an external cylinder 1 constituting the exterior of a double tube construction; an internal cylinder 2 formed by a porous metal plate constituting the interior of said double tube construction; hydrogen combustion catalyst 4 supported with precious metals on spherical ceramic support surface, formed in pellet state, being packed in said internal cylinder 2; an insert pipe 3 formed by porous metal plate inserted in the center of said internal cylinder 2; pre-heating heaters 5 installed between said insert pipe 3 and said internal cylinder 2 to preheat said hydrogen combustion catalyst 4 to ambient atmosphere of over catalytic reaction temperatures; a hydrogen introducing port 8 connecting to said insert pipe 3; an air introducing port 9 provided at the bottom of said external cylinder 1 in the area between said external cylinder 1 and said internal cylinder 2, wherein air for hydrogen combustion is introduced by the drift effect resulting from the differential pressure generated between the packed layer of hydrogen combustion catalyst and the outside, by thermal convection, achieving safe combustion treatment of hydrogen in simple construction, small size and high treatment efficiency.

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.

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.

A method of injecting mortar into a container fastened to a first tank and to a second tank, the first tank communicating with the container via a first orifice and the second tank communicating with the container by a second orifice, the method comprising the following operations: a continuous circulation of a first stream of mortar is made to flow in a circulation loop; during the continuous circulation, a second stream of mortar is drawn off from the circulation loop, the second stream being smaller than the first stream of mortar; the second stream of mortar is injected into the container, ensuring that there is dynamic confinement of the gaseous effluents; and the appearance of mortar in the second tank is monitored and, when this appearance is detected, the removal of mortar from the circulation loop is brought to an end.

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.

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

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.

Length adjustment can be performed in a simple manner and without impairment of the insulating effect in an insulation cassette for the heat insulation of elongated elements. A multilayer insulation includes flat reflection elements (21, 22). Each layer of the insulation has at least two of the flat reflection elements (21, 22), which overlap at least partly at their ends (24) facing each other.

A fine motion control rod drive mechanism handling apparatus attaches a fine motion control rod drive mechanism having a control rod drive mechanism body, a spool piece, a motor bracket and a motor unit to a reactor pressure vessel, and detaches it from the reactor pressure vessel. The fine motion control rod drive mechanism handling apparatus is provided with a bolt wrench assembly, a motor unit attachment mounted to the bolt wrench assembly, for meshing a first gear of a first gear coupling on a spool piece side with a second gear of a second gear coupling on a motor unit side, and a rotation mechanism mounted to the bolt wrench assembly, for rotating the motor unit attachment.