In various embodiments, safe collaboration between a robot and humans is achieved by operating the robot continuously at or below a first threshold speed at which any collisions with a person's arms do not cause harm, and, upon detection of the person's torso or head within a danger zone around the robot, reducing the speed to or below a second threshold at which any collisions with the person's torso or head do not cause harm.

There is provided a method for actuating a first key of a keyboard with a tracer finger of a robot. An exemplary method comprises acquiring parameters of the keyboard and determining a position of the first key as a function of the acquired parameters using a model of the keyboard. The exemplary method also comprises guiding the tracer finger of the robot to the determined position of the first key. The exemplary method additionally comprises actuating the first key with the tracer finger of the robot.

A walking robot having joints which move using a torque servo, a posture of the robot being stably controlled, and a method of controlling a posture of the robot. It is possible to maintain a stable angle of the upper body while keeping an erect posture and balance using the COG of the robot and the inclination and the direction of the upper body and the pelvis of the robot, even in an external variation including external force or an inclination angle of the ground. Even in a state in which terrain information is not known in advance, the robot may keep an erect posture in a direction of gravity. Even when a plane where the robot stands is gradually inclined, the postures of the upper body and the legs of the robot may be kept while actively changing the angle of the ankle joint.

A verification and control method for at least one water purification system is described, which includes a step of supplying, by a server embedded with the water purification system, an editing interface comprising a zone for selecting items of exploitation information representing physical quantities associated with the water purification system, a step of selecting, via the first remote browser, at least one item of exploitation information to constitute at least one exploitation interface page, a step of sending a request to access the exploitation page, by a second remote browser, to the server, a step of collecting the value of each physical quantity represented by a selected item of information to constitute the page, and a step of supplying, by the server, the page comprising each collected value.

A network system may be provided that includes an electronic product, a recognition target, a recognition device, a setting program and a display unit. The electronic product may operate to manage or process a target. The recognition target may include information relating to the target. The recognition device may recognize information listed on the recognition target. The setting program may convert information recognized by the recognition device into setting information. The display unit may display the setting information converted by the setting program.

An energy-reducing method and apparatus for retrofitting a single zone, constant volume HVAC system, with or without an economizer, that provides heating, cooling, and ventilation to occupants within a building space. The present invention includes the introduction of a programmable logic controller and variable frequency drive (VFD) that takes control of the existing fan, heating, cooling, and optional economizer operation. The reduction of the fan speed in the ventilation mode when the 100% operation is not needed saves significant energy of the existing constant volume HVAC system where the fan motor is designed to run 100% of the time.

An automatic-adjustable stacker for controlling the movement of a media, such as cardboard, through a media handling system. The stacker includes a media receiver positioned proximate a feed of the media that receives a leading edge of the media and a controller that causes the media receiver to move from a first position for receiving the media, to a second position for depositing of the media at a desired location. The media receiver is configured to prevent the media from coming into contact with other media already located at the desired location until the media has arrived at the desired location, while creating a concave-like shape to the media while conveying it.

An information processing apparatus for performing recognition processing by a recognizer for a position and orientation of a work subject to undergo work by a working unit of a robot arm. The information processing apparatus including an obtaining unit adapted to obtain, for each of a plurality of positions and orientations of the work subject, a position and an orientation of the working unit in which the working unit can perform the work, and a restriction unit adapted to restrict a position and an orientation of the work subject used in the recognition processing by the recognizer to a position and an orientation of the work subject corresponding to the position and the orientation of the working unit that have been obtained by the obtaining unit.

A work hanging apparatus includes a hanger line continuously conveying hangers each having a hook, a robot that has a hand with which a work having a hole is held and transfers the held work to a hanging location set in the hanger line, a controller controlling a movement of the hand to catch the hook of one of the hangers with the hole of the held work at the hanging location, a hole deviation detector that detects a positional deviation of the hole of the work, an attitude deviation detector that detects an attitudinal deviation of the hanger, and a corrector that corrects the movement of the hand according to the positional and attitudinal deviations.

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.

The presently disclosed subject matter provides compositions that selectively bind cyclooxygenase-2 and comprise a therapeutic and/or diagnostic moiety. Also provided are methods for using the disclosed compositions for diagnosing (i.e., by imaging) a target cell and/or treating a disorder associated with a cyclooxygenase-2 biological activity.

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.

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).

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.

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.

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 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 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.

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 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.

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.

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 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.

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.

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.

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 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.

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