Agency: European Commission | Branch: FP7 | Program: CP-IP | Phase: Fission-2010-2.3.1 | Award Amount: 10.12M | Year: 2011
In line with the Sustainable Nuclear Energy Technology Platform (SNETP) Strategic Research Agenda (SRA) and Deployment Strategy (DS), the ARCHER project will extend the state-of-the-art European (V)HTR technology basis with generic technical effort in support of nuclear cogeneration demonstration. The partner consortium consists of representatives of conventional and nuclear industry, utilities, Technical Support Organisations, R&D institutes and universities. They jointly propose generic efforts composed of: -System integration assessment of a nuclear cogeneration unit coupled to industrial processes -Critical safety aspects of the primary and coupled system: oPressure boundary integrity oDust oIn-core hot spots oWater and air ingress accident evaluation -Essential HTR fuel and fuel back end R&D oPIE for fuel performance code improvement and validation oBack end research focused on radiolysis -Coupling component development: oIntermediate heat exchanger development oSteam generator assessment -High temperature material R&D: oCompletion of graphite design curves oMaking use of the experience of state of the art metal in conventional industry -Nuclear cogeneration knowledge management, training and communication The activities proposed are imbedded in the international framework via GIF; direct collaboration within the project with international partners from the US, China, Japan, and the republic of Korea; and cooperation with IAEA and ISTC. The proposal is a technical building block supporting nuclear cogeneration as fossil fuel alternative for industry and as such supports a high potential contribution to European energy strategy as defined in the SET-Plan. The results of the proposal will be reported to SNETP, to support the strategic pillar of other uses of nuclear energy, and the establishment of a Nuclear Cogeneration Industrial Initiative, which shall include effective (international) nuclear cogeneration demonstration.
Westinghouse Electrical Germany GmbH | Date: 2014-09-16
The present disclosure relates to a reactor pressure-relieving filter system having an interior space hermetically enclosed by a pressure-resistant reactor casing, at least one pressure-relieving opening through the reactor casing, and a dry filter for a gas mass flow emerging from the pressure-relieving opening when there is excess pressure in the interior space. The filtering efficiency can depend both on the average dwell time of the gas mass flow in the dry filter and on the temperature difference between the gas mass flow and the respective dew point. A flow channel connects the pressure-relieving opening and the dry filter. A passive orifice plate is provided upstream of the dry filter in the flow channel.
Westinghouse Electrical Germany GmbH | Date: 2015-11-06
The invention relates to a narrow gap inspection system, having a tube to be inspected, in particular a boiler tube, which extends in the axial direction and, surrounding this at a radial distance with a hollow-cylindrical gap, a casing, in particular a casing tube. The casing has an axially extending opening with an opening angle running perpendicular to the axial direction, and radially over the opening there is provided an axially mobile support system which supports a ring which is arranged in the gap and is able to rotate about the tube and has an inspection device that can be placed over the tube by means of a respective axial movement of the support system and a respective rotation of the ring in the gap. The invention also relates to a method for installing a narrow gap inspection system.
WESTINGHOUSE Electrical GERMANY GMBH | Date: 2015-11-18
The invention relates to a nuclear facility pool cleaning device having a floating platform, capable of floating in water, having buoyancy bodies; a drive device for displacing the floating platform on the surface of a water-filled nuclear facility pool to be cleaned; a winching device connected to the floating platform; a pump which is winchable vertically by the winching device and has a vacuum hose, connected thereto at its first end, for cleaning the bottom of the nuclear facility pool; a remote control device for remotely operating at least the drive device and the winching device; an optional stationary external storage tank; and wherein the second end of the vacuum hose preferably leads at least indirectly into the stationary external storage tank.
Westinghouse Electrical Germany GmbH | Date: 2012-12-17
A steam generator heating tube repair sleeve has an encircling flange, conical region, and a straight region. The encircling flange merges into a conical region that tapers on the outside in the direction of the other sleeve end and which is adjoined to the straight region. A steam generator heating tube repair method is used to repair a steam generator heating tube that is installed in a steam generator having a defective tube end. The method includes conical milling out of the defective tube end, inserting a steam generator heating tube repair sleeve into the conically milled-out defective tube end, rolling in the steam generator heating tube repair sleeve, and welding the flange region.
WESTINGHOUSE Electrical GERMANY GMBH | Date: 2012-09-28
A condensation chamber cooling system of a condensation chamber for a boiling water reactor has a heat exchanger outside the condensation chamber. An elongate cooling module is provided in the condensation chamber with an evaporation space in its upper region. The cooling module is configured such that the evaporation space is located above a maximum filling level of the condensation chamber. The cooling module includes at least one riser pipe and one downpipe that issue with their upper ends into the evaporation space and with their lower ends in the condensation chamber. A first pressure line leads from the evaporation space to the heat exchanger and, from there, a second pressure line which issues in the condensation chamber below the minimum filling level. Thus, the condensation chamber, the pressure lines, the cooling module and the heat exchanger form a passive closed cooling circuit.
WESTINGHOUSE Electrical GERMANY GmbH | Date: 2014-06-03
A nuclear plant manipulator system is disclosed which can include a manipulator with an image acquisition device and remote-control drive, a remote-operating device, as well as an analysis device for analyzing image data of the image acquisition device. The analysis device can be configured in such a way that when the manipulator moves along a path of movement based on image data, respective known objects that are found along the path of movement are automatically identified, and when such an object is passed, depending on the direction, an object counter is incremented or decremented, whereby the current value of the object counter is provided to the remote-operating device. A method is disclosed for controlling a manipulator of the nuclear plant manipulator system.
Westinghouse Electrical Germany GmbH | Date: 2013-12-27
An erosion device and a corresponding method are disclosed for machining a hollow-cylindrical workpiece, wherein the device is elongated and/or formed in the manner of a tube or cylinder and is characterized in that at least two rotationally acting drives (A1, A2), each with a drive shaft (AW1, AW2), and also an erosion electrode (E), interacting with the drives (A1, A2) and formed in the manner of a ring or disc, are provided. The drives (A1, A2) and the electrode (E) are adapted in size and extent to the internal diameter of the workpiece (W) to be machined, so that the device can be introduced into the respective hollow-cylindrical workpiece (W) and can be positioned at the location respectively to be machined or the region to be machined in the workpiece (W), and the erosion electrode (E) can be pivoted or can be rotated by a coupled pivoting or rotating movement of the at least two drives (A1, A2)
WESTINGHOUSE Electrical GERMANY GMBH | Date: 2011-08-31
A fuel element storage and cooling configuration includes a fuel element storage pool and a cooling system having at least one first heat exchanger disposed in the fuel element storage pool and at least one second heat exchanger disposed in a heat sink and located at a distance therefrom, above a highest point of the first heat exchanger. The two heat exchangers are connected, using a pipe system, to form a closed circuit, which is at least partially filled with a flowable coolant. If the temperature of the first heat exchanger is increased with respect to the second heat exchanger, natural circulation of the coolant, and thus heat transport from the fuel element storage pool to the heat sink, is ensured without a pump apparatus.
Westinghouse Electrical Germany GmbH | Date: 2016-05-25
The invention is related to a filtered containment vent system for a nuclear power plant, comprising a flow conduit (12, 50, 72) for a gas stream (30, 82) to be filtered, with an upstream inlet (14) inside the containment (18) and a downstream outlet (16) at the edge of the containment (18), leading afterwards to outside the containment and comprising an aerosol filter (22, 40) arranged inbetween upstream inlet (14) and downstream outlet (16), wherein the aerosol filter (22, 40) comprises a demister unit (42) and at least two subsequent filter units (44, 46, 48). At least one PAR (Passive Autocatalytic Recombiner) cartridge (76, 78, 80, 92, 94, 96, 100) is foreseen in the flow conduit (12, 50, 72) inbetween its inlet (14) and its outlet (16) in order to recombine the hydrogen and carbon monoxide within the gas stream (30, 82) to be filtered.