v

Vitamin-targeted imaging agents

The invention relates to compounds and methods for targeting radionuclide-based imaging agents to cells having receptors for a vitamin, or vitamin receptor binding derivative or analog thereof, by using such a vitamin as the targeting ligand for the imaging agent. The vitamin-based compounds can be used to target radionuclides to cells, such as a variety of tumor cell types, for use in diagnostic imaging of the targeted cells.




v

HIV integrase inhibitors

The disclosure generally relates to the novel compounds of formula I, including their salts, which inhibit HIV integrase and prevent viral integration into human DNA. This action makes the compounds useful for treating HIV infection and AIDS. The invention also encompasses pharmaceutical compositions and methods for treating those infected with HIV.




v

Process for producing mixed metal rare earth metal halide solutions in organic solvents

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




v

Manufacture and use of modified polysaccharide chitosan bonds and a process to improve the preparation of HES-medicinal substance compounds

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




v

Light absorption anisotropic film, polarizing film, process for producing the polarizing film and display device using the polarizing film

A light absorption anisotropic film, wherein content of a liquid crystalline non-colorable low molecular weight compound is 30% by mass or less; and which is obtained by fixing the alignment of a dichroic dye composition comprising at least one type of azo-based dichroic dye having nematic liquid crystallinity; and shows a diffraction peak derived from a periodic structure in a direction parallel to the alignment axis on measurement of X-ray diffraction. The light absorption anisotropic film is high in dichroism.




v

Metallodrugs having improved pharmacological properties and methods of manufacture and use thereof

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.




v

Photo-responsive liquid crystalline compound and its applications

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




v

Photoreactive synthetic regulator of protein function and methods of use thereof

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.




v

Liquid-crystal compound, liquid-crystal composition, light absorption anisotropic film, and liquid-crystal display device

A liquid-crystal compound denoted by general formula (I) below wherein each of the groups is defined and Dye denotes an azo dye residue denoted by general formula (II) with X and n also being defined. The azo liquid-crystal compound is capable of orientation with a high degree of orientation order.




v

Visible/near-infrared porphyrin-tape/C60 organic photodetectors

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.




v

Androgen induced oxidative stress inhibitors

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




v

Container and method for transporting a syringe containing radioactive material

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.




v

Radioactive decontamination and translocation method

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.




v

Radioactive decontamination and translocation method

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.




v

Method for dissolving plutonium or a plutonium alloy and converting it into nuclear fuel

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.




v

Radioactive decontamination and translocation method

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.




v

Container transporting a syringe containing radioactive material

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.




v

Radioactive substance decontamination method and apparatus

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.




v

Container and method for transporting a syringe containing radioactive material

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.




v

Container and method for transporting a syringe containing radioactive material

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.




v

System and method for chemical decontamination of radioactive material

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.




v

Device for inspecting plant parts located under water

A device for inspecting submersed plant parts is particularly suited for ultrasonic inspection of screws in the core baffle of a nuclear reactor pressure vessel. The device includes a remote-controlled underwater vehicle that is provided at its end face with a carrier that can be pivoted about a pivot axis oriented parallel to the longitudinal central axis of the underwater vehicle, and is provided with a holding device for an inspection head that is arranged on the carrier spaced apart from the pivot axis.




v

Apparatus and method for mounting and moving a working apparatus on a structure for the performance of works on the structure

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.




v

Power conversion circuitry

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




v

Vol-oxidizer for spent nuclear fuel

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.




v

Separation and receiving device for spent nuclear fuel rods

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.




v

Liquid radioactive waste treatment system

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.




v

Flexible glove holder used in the opening of a glove box

The flexible glove holder (1) includes a flat structure (13) with three branches (2, 3 and 4) forming an S-shape on which the glove is wound. The holder (1) is then pushed into the opening of the glove box. This rapid action method makes it possible to avoid knotting the gloves when they must be drawn toward the outside for an operation within the box and also allows the implementation of biological protection on the opening of the glove box as well as a protection of the agents against radiation.




v

Low sintering temperature glass waste forms for sequestering radioactive iodine

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.




v

Mixed-layered bismuth-oxygen-iodine materials for capture and waste disposal of radioactive iodine

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.




v

Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

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




v

Reactor installation and removal tools

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.




v

Method for recovery of residual actinide elements from chloride molten salt

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.




v

Apparatus for treating radioactive nitrate waste liquid

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).




v

Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

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




v

Method for measuring the neutron flux in the core of a nuclear reactor using a cobalt detector and associated device

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.




v

Fine motion control rod drive mechanism handling apparatus and method of handling fine motion control rod drive mechanism

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




v

Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system

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.




v

Polypeptides with permease activity

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.




v

Pharmaceutical formulations comprising an insulin derivative

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.




v

Dual variable domain immunoglobulins and uses thereof

The present invention relates to engineered multivalent and multispecific binding proteins, methods of making, and specifically to their uses in the prevention, diagnosis, and/or treatment of disease.




v

Temperature sensitive conjugate compositions

This disclosure relates to temperature sensitive conjugates, compositions, and uses related thereto. In certain embodiments, the disclosure relates to conjugate polymers comprising a) a temperature sensitive polymer and b) an antibody. Typically the antibody has an epitope to a platelet receptor. The antibody may be a single-chain antibody wherein the platelet receptor is GPIIb/IIIa, such as an anti-GPIIb/IIIa antibody. In certain embodiments, the antibody binds specifically to the activated conformation of GPIIb/IIIa, i.e., an activation-specific GPIIb/IIIa antibody.




v

CX3CR1-binding polypeptides comprising immunoglobulin single variable domains

The present invention relates to CX3CR1-binding polypeptides, in particular polypeptides comprising specific immunoglobulin domains. The invention also relates to nucleic acids encoding such polypeptides; to methods for preparing such polypeptides; to host cells expressing or capable of expressing such polypeptides; to compositions comprising such polypeptides; and to uses of such polypeptides or such compositions, in particular for prophylactic, therapeutic and diagnostic purposes.




v

Method for providing a β-lactoglobulin product and an α-enriched whey protein isolate

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.




v

Muteins of hNGAL and related proteins with affinity for a given target

The present invention relates to novel muteins derived from human lipocalin 2 (hNGAL) and related proteins that bind a given non-natural ligand with detectable affinity. The invention also related to corresponding nucleic acid molecules encoding such a mutein and to a method for their generation. The invention further relates to a method for producing such a mutein. Furthermore, the invention is directed to a pharmaceutical composition comprising such a lipocalin mutein as well as to various uses of the mutein.




v

Antibody molecules having specificity for human OX40

The invention relates to antibody molecules having specificity for antigenic determinants of human OX40, therapeutic uses of the antibody molecules and methods for producing said antibody molecules.




v

Derivatisation of granulocyte colony-stimulating factor

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.




v

Long-acting gastrin derivatives

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




v

Anti-serum albumin binding variants

The invention relates to improved variants of the anti-serum albumin immunoglobulin single variable domain DOM7h-11, as well as ligands and drug conjugates comprising such variants, compositions, nucleic acids, vectors and hosts.




v

Monitoring user activity on a mobile device

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.