The invention relates to a gear wheel pump with two meshing gear wheels which are rotatably mounted within a pump housing by means of a driven driveshaft and a crankshaft journal and which form a pumping channel system between a pump inlet and a pump outlet. Several gaps are formed between the pump housing, the gear wheels, the driveshaft, and the crankshaft journal. One of the gaps between the driveshaft and one of the gear wheels contains means for the rotationally fixed connection of the driveshaft to the gear wheel. In order to prevent leakages penetrating to the connecting means, according to the invention the gap between the driveshaft and the gear wheel is sealed, with respect to the front faces of the gear wheel, by means of a sealant.

A combined CV joint boot and inner seal includes a boot portion having a first end and a second end and having a shaft sealing portion at the first end for sealing with a first shaft of the CV joint. A front can sealing portion is positioned at the second end of the boot portion. An inner seal portion extends generally inwardly towards the CV joint longitudinal axis to block lubricant from migrating into the interior of the boot portion.

In a scroll compressor of the present invention, a fixed scroll 11 and an orbiting scroll 12 are meshed with each other such that spiral laps of the fixed scroll 11 and the orbiting scroll 12 inwardly face each other, an Oldham ring 26 is provided between the main bearing member 19 and the orbiting scroll 12, and a key portion of the Oldham ring 26 is inserted into a key groove 19a of the main bearing member 19. Grooves 19b are formed in Oldham ring 26 sliding surfaces on both sides of the key groove 19a. According to this configuration, the Oldham ring 26 and the main bearing member 19 can be restrained from coming into contact with each other in the vicinity of the bearing key groove 19a, and restrained from vibrating, and it is possible to provide an inexpensive scroll compressor of low noise.

A coupling for connecting a rotating tube cleaning shaft to a tube cleaning machine where high pressure fluid is pumped through the coupling, where the coupling is sealed to contain the high pressure fluid, and where a machine driven rotary flexible shaft passes through the coupling.

A device for generating limit torque with a function of yielding a torque change in real time includes a spring, a rotating portion having a cam surface formed therein, a transmitting portion transmitting an elastic force of the spring to the cam surface, a fixed portion with respect to which the relative rotation of the rotating portion is generated, and a limit-torque control portion provided to the fixed portion so as to control limit torque of the rotating portion by adjusting the elastic force of the spring. In the device, the limit-torque control portion controls the limit torque of the spring by changing the elastic force of the spring in real time.

An electro-mechanical energy conversion device is provided having an armature with a central cavity. The armature is rotatably mounted in a frame. A torsion bar is positioned within the armature with one end connected to the armature and the other end connected with an energy source or consuming device.

A system and methods are provided for controlling a motor of a rod pumping system using previous RPMs of the motor and predicting an RPM of the motor; correcting a power factor of a motor of a rod pumping system; allocating energy consumption and allocating energy generation for a set of wells connected to an electricity meter using an amount of energy generated by each well; and generating an alert if a set of data is beyond a threshold for the set of data.

Shed formation on a weaving machine (2), which is driven by a main motor (3), with a shedding device (4), which is driven by a shedding motor (5), wherein in each motion cycle (N) of the weaving machine (2), a loom shed (7) formed by warp threads (8) of the weaving machine (2) is opened and closed dependent on a weave pattern, and wherein the synchronicity of the two motors (3, 5) is controlled by signals (10) of a control device (9). During a partial number (Tn1, Tn2) of motion cycles (N), the synchronicity of the two motors (3, 5) is changed in such a manner so that plural shed closure angles (FSW) at which the loom shed (7) in the respective motion cycles (N) is closed, form an increasing or decreasing sequence.

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.

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.

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

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.

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.

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.

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 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.

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.

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.

A storage rack arrangement (10) for the storage of nuclear fuel elements in a storage pool includes at least two storage racks (1.1-1.3) which each contain a plurality of vertical channels (9) arranged next to one another for the reception of the fuel elements, with positioning elements (6) being provided at the storage racks at the bottom. The storage racks are connected to one another at the top and the storage rack arrangement (10) additionally includes one or more base plates (2.1-2.3) which are provided with positioning members (8) which fit with the positioning elements (6) of the storage racks (1.1-1.3) and which, together with the positioning elements, position the storage racks with respect to the base plate or base plates (2.1-2.3) to prevent a displacement of the storage racks on the base plate or plates.

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.

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.

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.

The invention relates to a polypeptide having a mutation at one or more position corresponding to T219 of SEQ ID NO: 55, wherein the polypeptide has at least 50% sequence identity with SEQ ID NO: 55, and wherein the polypeptide has permease activity.

Acylated insulins wherein an acyl moiety is attached to the parent insulin and wherein the acyl moiety comprises repeating units of alkylene glycol containing amino acids and wherein there is only one lysine residue (K & Lys) in the parent insulin, having satisfactory properties when administered pulmonary.

Methods for treating fatty liver disease, e.g., hepatic steatosis, using peptide fragments of the C-terminal end of glucagon-like peptide-1 (GLP-1), e.g., GLP-1(28-36).

A system that incorporates teachings of the present disclosure may include, for example, a set top box (STB) comprising a controller programmed to receive measurement data stored in a first wireless device serving as a portable monitoring gateway that collects subscriber collected data and store and analyze the measurement data at the STB using the received measurement data received from the first wireless device and optionally from a remote server or a local storage space having stored measurement data to provide analyzed results. Other embodiments are disclosed.

A system or method for inferring and selective display of visual and sound media content based on a pet(s)'s level of engagement or reactions to content displayed on any number of content display devices including, but not limited to, television screens, computer monitors, tablets, and cell phones and measured by a sensor. A content selection algorithm takes as input the sensor measurements and historical or pre-computed data to infer the pet(s)'s preference for content. A content modification algorithm interposes algorithmically computed shapes and sounds overlaid on top of the existing content to attract the attention of the pet(s) observing the display.

A method and apparatus for detecting triggering events in a data stream, comprising extracting audio portions from the data stream, detecting a sequence of one or more Dual Tone Multiple Frequency (DTMF) signals representing the events from the extracted audio portions, and logging data representative of the sequence of DTMF signals into a database.

A method includes receiving, at a multimedia device, a data stream representing multimedia content, the data stream comprising first timing information for the multimedia content, and metadata representing interactive event information associated with the multimedia content, the metadata comprising second timing information for the interactive event information. During the playback of the multimedia content, a first user interactive event is identified that is associated with a first time point in the playback of the multimedia content based on the interactive event information, and the first user interactive event is performed concurrent with the first time point in the playback of the multimedia content.

An early warning system is provided. The early warning system includes a plurality of sensors, a server, and an information appliance device. The sensors produce status information. The server produces event information according to the status information of the sensors, transforms the event information into a first multimedia signal, and transmits the first multimedia signal to the information appliance device through a computer network. The information appliance device is connected to a display device, wherein the information appliance device transforms the first multimedia signal into a second multimedia signal capable of displaying through the display device. The disclosure further provides an early warning server, an early warning method, and a computer program product for report information.

An inflight entertainment (IFE) system preloads from head end equipment onto seat end video caches subsets of prerecorded video entertainment programs from a library of prerecorded video entertainment programs stored on the head end equipment. Preloading is done independent of play requests made by passengers using the IFE system. The selected subsets are selected using selection metrics such as program popularity, passenger demographics and/or passenger preferences. The same or a different subset may be selected for different passengers. As a result of the selective preloading of the seat end video caches, if the head end equipment or the distribution system becomes inoperable during the flight, the IFE system is able to continue to deliver a limited offering of popular, demographically indicated and/or passenger preferred video entertainment from the seat end video caches, without requiring a large multiplier in storage capacity or loading time.

System and method for providing a probabilistic order of tiles relative to a current section of a video that a user is viewing. A cache implementation uses this ordering to decide what tiles to evict from the cache, i.e. which tiles will probably not be accessed within a particular timeframe, but not when to evict (this is up to the cache implementation). A cache implementation can also use the prioritized list of the present embodiment to pre-fetch tiles.

An electronic device with one or more processors, memory and a display receives a first request to display a first video stream on the display. In response to receiving the first request, the electronic device displays the first video stream on the display. While displaying the first video stream on the display, the electronic device receives a second request to display a second video stream on the display. In response to receiving the second request, the electronic device displays at least a portion of the first video stream on the display concurrently with at least a portion of the second video stream, where the second video stream was received, at least in part, from a content source in response to a request from the electronic device to the content source for delivery of the second video stream from the content source.

Methods, systems, and computer readable media for measuring multicast latency are disclosed. According to one method, the method includes emulating one or more Internet protocol television (IPTV) user devices by generating channel leave and join requests. The method further includes monitoring network responses to the channel leave and join requests and calculating, during a cycle of channel leave and join requests for a user device and prior to repeating the cycle, at least one metric of latency associated with the channel leave and join requests.

A solar cell sealing film contains an ethylene-unsaturated ester copolymer, a crosslinker, and crosslinking auxiliary agents, wherein the solar cell sealing film contains a polyfunctional (meth)acrylate having 5 or more (meth)acryloyl groups in the molecule and triallyl isocyanurate as the crosslinking auxiliary agents, and a mass ratio of the polyfunctional (meth)acrylate to the triallyl isocyanurate is 0.06 to 0.3 parts of polyfunctional (meth)acrylate per 1 part of triallyl isocyanurate.

Disclosed is a hot-dip galvanized steel sheet or an alloyed hot-dip galvanized steel sheet, which has a tensile strength of 980 MPa or more, excellent workability, high yield ratio and high strength. The hot-dip galvanized steel sheet or the alloyed hot-dip galvanized steel sheet is characterized by containing 0.12-0.3% by mass of C, 0.1% by mass or less (excluding 0% by mass) of Si, 2.0-3.5% by mass of Mn, 0.05% by mass or less (excluding 0% by mass) of P, 0.05% by mass or less (excluding 0% by mass) of S, 0.005-0.1% by mass of Al and 0.015% by mass or less (excluding 0% by mass) of N, with the balance made up of iron and unavoidable impurities. The hot-dip galvanized steel sheet or the alloyed hot-dip galvanized steel sheet is also characterized in that the metallic structure thereof contains bainite as a matrix structure, and the area ratio of ferrite is 3-20% and the area ratio of martensite is 10-35% relative to the entire structure.