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 preferred embodiment may generally be construed as providing a method for storing fissile material, such as spent nuclear fuel (SNF), and includes the steps of: providing a storage container configured to receive the fissile material therein; and applying a coating to a surface of the storage container. Preferably, the coating is formed, at least in part, of a neutron-absorbing material and is adapted to reduce neutron multiplication and/or provide a shielding of the fissile material received within the storage container. Systems also are provided.

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.

In a chemical decontamination method of chemically decontaminating radioactive nuclides from a metallic material, oxalic acid and hydrazine are injected as a reductive decontaminating agent into water that is in contact with the metallic material. Injection of the hydrazine is stopped after a cation resin arranged in a circulation line connected to the metallic material breaks, and at least the oxalic acid and the hydrazine in the reductive decontaminating agent are decomposed using a decomposing catalyst.

A method and apparatus for transporting syringes containing radioactive material. The apparatus includes a radiopharmaceutical pig having an inner chamber in which a sharps container can be secured. The sharps container has a housing and an attachable cap. The method includes assembling the radiopharmaceutical pig so that the chamber of the radiopharmaceutical pig contains the syringe in the sharps container housing. The radiopharmaceutical pig is disassembled, where upon the syringe is removed, discharged, and then replaced in the sharps container housing. The cap of the sharps container is affixed to the housing of the sharps container, thus enclosing the contaminated syringe therein. The radiopharmaceutical pig is assembled so that its chamber contains the sharps container and the syringe. The radiopharmaceutical pig is transported to a disposal area, where it is disassembled and the sharps container containing the syringe is placed in a particular disposal container.

A method and apparatus for transporting syringes containing radioactive material. The apparatus includes a radiopharmaceutical pig having an inner chamber in which a sharps container can be secured. The sharps container has a housing and an attachable cap. The method includes assembling the radiopharmaceutical pig so that the chamber of the radiopharmaceutical pig contains the syringe in the sharps container housing. The radiopharmaceutical pig is disassembled, where upon the syringe is removed, discharged, and then replaced in the sharps container housing. The cap of the sharps container is affixed to the housing of the sharps container, thus enclosing the contaminated syringe therein. The radiopharmaceutical pig is assembled so that its chamber contains the sharps container and the syringe. The radiopharmaceutical pig is transported to a disposal area, where it is disassembled and the sharps container containing the syringe is placed in a particular disposal container.

A method for chemically decontaminating radioactive material. The method includes reducing-dissolving step for setting surface of radioactive material in contact with reducing decontamination liquid including mono-carboxylic acid and di-carboxylic acid as dissolvent; and oxidizing-dissolving step for setting the surface of the radioactive material in contact with oxidizing decontamination liquid including oxidizer. The method may include repeated pairs of steps, each pair including the reducing-dissolving step and the oxidizing-dissolving step. The mono-carboxylic acid may include formic acid, and the di-carboxylic acid includes oxalic acid. The oxidizer may be ozone, permanganic acid or permanganate.

A 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.

Decontamination of nuclear facilities is necessary to reduce the radiation field during normal operations and decommissioning of complex equipment. In this invention, we discuss gel and foam based diphosphonic acid (HEDPA) chemical solutions that are unique in that these solutions can be applied at room temperature; provide protection to the base metal for continued applications of the equipment; and reduce the final waste form production to one step. The HEDPA gels and foams are formulated with benign chemicals, including various solvents, such as ionic liquids and reducing and complexing agents such as hydroxamic acids, and formaldehyde sulfoxylate. Gel and foam based HEDPA processes allow for decontamination of difficult to reach surfaces that are unmanageable with traditional aqueous process methods. Also, the gel and foam components are optimized to maximize the dissolution rate and assist in the chemical transformation of the gel and foam to a stable waste form.

A variable-voltage variable-frequency power source for an electric motor that drives a re-circulation pump for a boiling water nuclear reactor. The power source has a semiconductor electric power converter and a speed controller for controlling the semiconductor electric power converter. When a part of the semiconductor electric power converter comes into an inoperative state, that part is electrically disconnected, and the variable-voltage variable-frequency power source temporarily stops outputting power, thereby idling the re-circulation pump. Thereafter, the power source re-starts outputting power before the re-circulation pump completely stops. Thus, the re-circulation pump keeps operating, without stopping.

Frames are disclosed for mounting windows within the walls of enclosures for isolating or sealing substances such as radioactive or other hazardous substances from the surrounding environment. In a first embodiment of the present invention, a window assembly includes a two-piece frame that is welded into the wall of an enclosure. In a second embodiment of the present invention, a window assembly includes a three-piece frame that is clamped to the wall of an enclosure. The frame assemblies may also be used to mount structures other than windows to enclosure walls, such as ducts or pipes intended for passing power, gas, vacuum, or other utilities into the interior of an enclosure.

A working apparatus has: a working equipment for doing works on a structure; an operation mechanism adapted to actively move the working equipment relative to the structure; and an adhering/traveling module coupled to the operation mechanism and adapted to adhere to the structure so as to have the weight of the working apparatus borne by the structure and travel/move on the structure for positioning. With this arrangement, the working apparatus can perform accurate positioning operations in a narrow environment and complex scanning operations by means of various pieces of the working equipment such as inspection sensors, and can secure a large working area within a short period of time and reduce the overall working hours.

A 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.

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.

Frames for mounting windows within the walls of enclosures for isolating or sealing substances such as radioactive or other hazardous substances from the surrounding environment. In a first embodiment of the present invention, a window assembly includes a two-piece frame that is welded into the wall of an enclosure. In a second embodiment of the present invention, a window assembly includes a three-piece frame that is clamped to the wall of an enclosure. The frame assemblies may also be used to mount structures other than windows to enclosure walls, such as ducts or pipes intended for passing power, gas, vacuum, or other utilities into the interior of an enclosure.

A system and method for a self-charging battery cell are provided in which beta emissions from a Strontium-90 source are obtained by a sensor device and converted into electric energy. In embodiments, a scintillation device is used to intake emissions from a Strontium-90 source, and consequently emit a light or plurality of light flashes. A sensor device, e.g., a photodiode, is utilized to convert the light or plurality of light flashes into electric voltage, current and/or energy.

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 method for recovery of residual actinide element from chloride molten salts that are formed after electro-refining and/or electro-winning of a spent nuclear fuel and include actinide elements and rare-earth elements is provided. The method comprises conducting electrolysis using a liquid cadmium cathode (LCC) in the chloride molten salt that is formed after electro-refining and/or electro-winning of a spent nuclear fuel and contains rare-earth elements and actinide elements; electro-depositing the actinide elements contained in the chloride molten salt on the LCC in order to reduce a concentration of the actinide elements; and adding a CdCl2 oxidant to the chloride molten salt containing the LCC-metal alloy in order to oxidize the rare-earth elements co-deposited on the LCC, thereby forming the rare-earth chlorides in the chloride molten salt.

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between −10 et −20 MPa are made from an alloy with a content of Sn between Sn=(=0.025σ−0.25)% and Sn=−0.05σ%: those components subjected to such a stress of between 0 et −10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05σ+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07σ+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%. A fuel assembly made according to the method.

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

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

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 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 is a process of stabilizing spent filter material that comprises mixing the filter media with a city media to produce a composition having a moisture content that is sufficiently low to retard microbial growth. The composition comprises spent filter media and a dry material, and preferably comprises diatomaceous earth. Soil is treated by adding the composition as a top dressing, soil amendment, or the like.

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.

Capture compounds and collections thereof and methods using the compounds for the analysis of biomolecules are provided. In particular, collections, compounds and methods are provided for analyzing complex protein mixtures, such as the proteome. The compounds are multifunctional reagents that provide for the separation and isolation of complex protein mixtures. Automated systems for performing the methods also are provided.

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.

Human antibodies, preferably recombinant human antibodies, that specifically bind to human interleukin-12 (hIL-12) are disclosed. Preferred antibodies have high affinity for hIL-12 and neutralize hIL-12 activity in vitro and in vivo. An antibody of the invention can be a full-length antibody or an antigen-binding portion thereof. The antibodies, or antibody portions, of the invention are useful for detecting hIL-12 and for inhibiting hIL-12 activity, e.g., in a human subject suffering from a disorder in which hIL-12 activity is detrimental. Nucleic acids, vectors and host cells for expressing the recombinant human antibodies of the invention, and methods of synthesizing the recombinant human antibodies, are also encompassed by the invention.

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.

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.

The disclosure relates to anti-glial maturation factor beta (“GMF-B”) monoclonal antibodies (mAbs) and fragments thereof, as well as hybridoma lines that secrete antibodies or fragments. Therapeutic and diagnostic uses of such antibodies, including treatment and detection of cancer and dementia, and methods and kits for detecting cells or samples expressing GMF-B, including soluble GMF-B, are also encompassed.

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.

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).

Provided are a support for affinity chromatography which has excellent alkali resistance, and a method for isolating immunoglobulin. A support for affinity chromatography, containing an immobilized protein ligand represented by the following formula (1): R—R2 (1) wherein R represents a polypeptide consisting of 4 to 30 amino acid residues that contains an amino acid sequence represented by ATK or ASK; and R2 represents a polypeptide consisting of 50 to 500 amino acid residues containing an immunoglobulin-binding domain consisting of an amino acid sequence represented by SEQ ID NO: 1 or SEQ ID NO: 2, the partial sequence thereof, or an amino acid sequence having 70% or more identity to these sequences; with the proviso that a terminus at which R2 binds to R is C-terminus or N-terminus of the immunoglobulin-binding domain.

The present disclosure relates to a Co-029 inhibitor for inhibiting the migration of cancer cells which express Co-029. The disclosure relates to a Co-029 inhibitor for the treatment of cancer and/or the prevention of cancer metastasis and pharmaceutical compositions comprising said inhibitor and provides Co-029 antibodies. The disclosure provides a method for predicting the response of a patient afflicted with or susceptible to be afflicted with cancer to a medical treatment with a Co-029 inhibitor, a method for diagnosing a cancer in a patient and a method for predicting the survival in a cancer patient.

The present invention relates to methods for forming dicarba bridges in organic compounds. This involves the use of a pair of complementary metathesisable groups on the organic compound, and subjecting the compound to cross-metathesis under microwave radiation conditions. In an alternative, the compounds contain a turn-inducing group between the pair of cross-metathesisable groups to facilitate the cross-metathesis.

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.

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.

An automatic content recognition (ACR)-enabled connected TV device may be associated with a paired device and the paired device may comprise a browser. The ACR-enabled connected TV device may be operable to enable, utilizing an ACR system, the browser to display, within a section of a browser window, interactive content related to certain content being presented by the ACR-enabled connected TV device. The ACR-enabled connected TV device may be operable to enable, utilizing the ACR system, a viewer to interact with the interactive content. The section of the browser window may be changed dynamically. The certain content may comprise an advertisement of a particular product and the interactive content may comprise a link to a website and/or other information related to the particular product. The certain content may comprise a program associated with a network and the interactive content may comprise information on polling questions related to the program.

A system and method in a television system for presenting information associated with a user-selected object in a television program is provided. An identity of a user-selected object in a television program being presented to a user is determined. Based at least in part on the identity of the user-selected object in the television program, information to present to the user is determined. The determined information is presented to the user on a television display.

Disclosed herein is a system and method for simultaneously broadcasting video components (VSs). In one example, a method includes an automation-system (AS) selecting a log entry including (i) a first identifier that maps to a first VC, and (ii) a second identifier that maps to a second VC; a recording-and-playout device (RAPD) retrieving the first VC; the RAPD sending the retrieved first-VC to an encoder; the encoder generating a first transport-stream (TS) having (i) program-identification (PID) data, and (ii) payload data including the sent first-VC; the encoder sending the generated first-TS to a first outbound-broadcast device (OBD); the encoder sending the generated first-TS to a transport-stream splicer; the AS loading the splicer with the second VC; the splicer generating a second TS having (i) the PID data of the generated first-TS, and (ii) payload data including the loaded second-VC; and the splicer sending the generated second-TS to a second OBD.

A virtual channel table for broadcasting protocol and a method for broadcasting by using the virtual channel table includes identification information identifying and permitting discrimination of active and inactive channels contained in the virtual channel table. At a receiver, the virtual channel table transmitted from the transmitting side is parsed, thereby determining whether the current received channel is an active or inactive channel.

Video thumbnail electronic program guide (EPG) systems and methods are operable to include a video thumbnail. An exemplary embodiment receives a media content stream at a media device; picks a plurality of still image video frames from the received media content stream, wherein each still image video frame has information that is sufficient to construct the still image video frame; generate a plurality of still image video frame thumbnails, wherein each of the still image video frame thumbnails correspond to one of the still image video frames; generate a video thumbnail from the plurality of still image video frame thumbnails; and incorporate the video thumbnail with at least one program descriptor and a channel identifier associated with the media content stream into the video thumbnail EPG.