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.

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.

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 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.

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.

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.

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 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.

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.

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.

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.

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.

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 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.

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.

The invention concerns a soluble pharmaceutical formulation comprising an insulin derivative wherein the formulation further comprises more than 4 zinc atoms per 6 molecules of the insulin derivative, and a citric acid monohydrate and/or a histidine compound used in an amount sufficient to increase the tendency of the insulin derivative to self-associate into dodecamers. The invention further comprises a process for preparing the soluble pharmaceutical formulation.

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.

Disclosed herein are compounds that inhibit Hsp90 interactions with IAP proteins, such as Survivin, XIAP, cIAP1, or cIAP2, and methods for identifying and using such compounds.

A method of producing a molecularly-imprinted material comprises synthesizing a peptide, oligosaccharide or oligonucleotide on a disposable surface modified support to produce a support surface-attached peptide, oligosaccharide or oligonucleotide, providing a selected monomer mixture, contacting the monomer mixture with the support surface-attached peptide, oligosaccharide or oligonucleotide, initiating polymerisation or at least one crosslinking reaction, dissolving or degrading the support surface-attached peptide, oligosaccharide or oligonucleotide and support, and obtaining molecularly imprinted material.

The present invention relates to isolation of whey proteins and the preparation of a whey product and a whey isolate. In particular the present invention relates to the isolation of a β-lactoglobulin product and the isolation of an α-enriched whey protein isolate from whey obtained from an animal. The α-enriched whey protein isolate provided by the present invention is besides from being low in β-lactoglobulin also high in α-lactalbumin and immunoglobulin G.

Three conjugation methods for use with the capsular saccharide of Streptococcus agalactiae. In the first method, reductive animation of oxidized sialic acid residue side chains is used, but the aldehyde groups are first aminated, and then the amine is coupled to a carrier via a linker. In the second method, sialic acid residues and/or N-acetyl-glucosamine residues are de-N-acetylated to give amine groups, and the amine groups are coupled to a carrier protein via a linker. In the third method, linkage is via galactose residues in the capsular saccharide rather than sialic acid residues, which can conveniently be achieved using galactose oxidase.

A composition having proanthocyanidin compounds having an average degree of polymerization of at least about 6. A method of administering to an immunosuppressed patient or a patient diagnosed with sepsis or septic shock a composition having a proanthocyanidin. A method of administering to a patient diagnosed with a gram negative bacterial infection a composition having proanthocyanidin compounds having an average degree of polymerization of at least about 6.

The present invention relates to a compound which is a polysaccharide derivative of GCSF, or of a GCSF like protein, wherein the polysaccharide is anionic and comprises between 2 and 200 saccharide units. The present invention also relates to pharmaceutical compositions comprising the novel compounds, and methods for making the novel compounds.

The present invention relates to gastrin derivatives comprising gastrin or an analogue or fragment thereof and a derivatisation group and therapeutic use thereof.

The present invention relates to novel antibodies, particularly antibodies directed against deletion mutants of epidermal growth factor receptor and particularly to the type III deletion mutant, EGFRvIII. The invention also relates to human monoclonal antibodies directed against deletion mutants of epidermal growth factor receptor and particularly to EGFRvIII. Diagnostic and therapeutic formulations of such antibodies, and immunoconjugates thereof, are also provided.

A location aware user interface on a wireless handset is described. The location aware user interface comprises a location module configured to transmit a location message to a remote server via a network. The remote server is configured to determine whether the wireless handset is within a geofence. The user interface further comprises a display module configured to display at least one content item associated with the geofence. The user interface also comprises an input module configured to receive a user-created content item and transmit the received user-created content item to the remote server. The remote server is configured to associate the content item with the geofence in which the wireless handset is located.

Monitoring user activity on a mobile device is described. In one aspect, video content is received and played to a user of the mobile device. The monitoring activity detects an interruption of playback of the video content and determines an event associated with the interruption. The event is stored in the mobile device and communicated to a remote device.

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.

Sponsored-content may be placed based on images in video content. A first image in a frame of a video content item is identified. The first image is matched with a second stored image. A sponsored-content item to be presented is selected based on an association between the second stored image and the sponsored-content item.

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.

A display device such as a TV has both HDMI and IP network interfaces and uses the HDMI interface to exchange IP network parameters with an audio video application module (AVAM) upon HDMI connection. In this way, an IP-based peer-to-peer or client-server network connection can be automatically established to promote faster communication when sharing and executing applications between the devices than is typically available over the CEC link of HDMI.

An interactive television program guide system with program series reminder and recording capabilities is provided. The system allows a user to set a reminder or schedule a recording for a single episode or for each episode of a program series. In addition, other options may be provided that allow the user to determine, for example, whether to schedule reminders/recordings for episodes on all channels on which the program airs or only on a selected channels, whether to schedule reminders/recordings for all episodes including reruns or only new episodes, whether to schedule reminders/recordings for network or syndicated episodes, and whether to schedule reminders/recordings for episodes on all days or only on selected days of the week. Before the scheduled broadcast time of each episode of each selected program series, the system sends a reminder message to the user that reminds the user of the program episode or sends a record command to a videocassette recorder to initiate recording of the episode. The system allows a user to view a list of all currently requested program reminders and scheduled program recordings. The user may update, change, or cancel any entry in either list or the system may automatically update the lists to match new broadcast schedule information. If the user sets a reminder or schedules a recording that conflicts with an existing reminder or recording, the system may inform the user of the conflict and allow the user to resolve the conflict or the system may resolve the conflict.