Abstract: A Process for selecting a Precoding Matrix Index (PMI) in a Multiple In Multiple Out (MIMO) receiver of a wireless communications comprising a base station communicating with User Equipments through a downlink and uplink channel, said base station applying a precoding on the transmit symbol vector based on a matrix Pi being selected from a set of predefined matrices and identified by a PMI index computed by said UE and forwarded to said base station via said uplink; said process involving step of: —estimating (100) the MIMO channel matrix H of a given set of resources blocks comprising received symbol vectors; —estimating (200) the variance ?2 of the additive noise (AWGN)—computing (300) for each particular matrix comprised within said set of predefined matrix a cost function Fi (Pi, H, ?2n) being representative of the orthogonality of said matrix MIMO channel matrix H; —comparing (400) the values of said cost function Fi; and —transmitting (500) to said base station the index i corresponding to the Fi repres

Abstract: A method for multi-level data transmission includes encoding a data signal to be transmitted into N multi-level signals in accordance with an encoding table, where the data signal is characterized with a stream of binary data segments each of which has a data length of M bits, transmitting simultaneously the N multi-level signals through N data transmission channels, respectively; and decoding the N multi-level signals into the data signal by comparing each two of the N multi-level signals transmitted through the two data transmission channels to obtain a respective bit of the M bits of each binary data segment of the data signal based on comparison between the two corresponding multi-level signals.

Abstract: An apparatus for determining a target precoding matrix from a plurality of precoding matrix candidates is provided. The apparatus includes a covariance matrix value provider, a real part determiner and a precoding matrix determiner. The precoding matrix determiner is adapted to determine the target precoding matrix from the plurality of precoding matrix candidates, wherein the precoding matrix determiner is configured to determine the target precoding matrix based on at least one of the one or more real covariance values.

Abstract: A modulated impulse generating apparatus includes a source signal generator that generates a source signal, a first oscillation unit that, when activated, a signal having extracts a desired frequency component from the source signal generated by the source signal generator and causes amplitude of the extracted signal to increase, a second oscillation unit that, receives input of a signal caused to increase by the first oscillation unit, and that, when activated, causes amplitude of the input signal to increase together with the first oscillation unit and outputs a modulated impulse modulated wave, and an activation unit that activates the first oscillation unit after the source signal generated by the source signal generator has been input to the first oscillation unit and activates the second oscillation unit after a certain time period has elapsed and oscillation amplitude of the input signal has increased.

Abstract: A circuit device includes a communication circuit that includes at least one of a reception circuit and a transmission circuit, and an adjustment signal generating circuit that outputs an adjustment signal which adjusts a transconductance of an adjustment target circuit included in the communication circuit. The adjustment signal generating circuit performs a generation process of the adjustment signal, accumulates charge corresponding to the generated adjustment signal in a capacitor, and outputs the adjustment signal based on the charge accumulated in the capacitor to the adjustment target circuit.

Abstract: A frequency modulator includes a digitally-controlled oscillator (DCO) arranged for producing a frequency deviation in response to a modulation tuning word and a phase-locked loop (PLL) tuning word. In addition, another frequency modulator includes a DCO and a DCO interface circuit. The DCO is arranged for producing a frequency deviation in response to an integer tuning word and a fractional tuning word. The DCO interface circuit is arranged for generating the integer tuning word and the fractional tuning word to the DCO, wherein the fractional tuning word is obtained through asynchronous sampling of a fixed-point tuning word.

Abstract: A communication method includes detecting at a gate drive unit a change of state of a command signal that is received via a command link of the gate drive unit and initiating, responsive to the change of state of the command signal, a blanking period in which the gate drive unit will process as incoming data any further changes of state of the command signal. The method also includes receiving incoming data at the gate drive unit, by processing modulations of the command signal, within the blanking period.

Abstract: An apparatus for decoding a received signal is provided. The received signal has been transmitted by conducting a transmission. The apparatus for decoding includes a detector and a filter application unit. The detector is configured to detect whether the transmission is a SU-MIMO transmission or a MU-MIMO transmission. The filter application unit is configured to apply either a first receive filter or a second different receive filter on the received signal depending on whether the transmission is the SU-MIMO transmission or the MU-MIMO transmission.

Abstract: Various devices and methods are provided that use signaling to support advanced wireless receivers. For example, a method includes receiving an input signal at a user equipment. The input signal includes a desired signal and an interfering signal, where the desired signal defines symbols using constellations. The method also includes obtaining information identifying a wireless channel used by the interfering signal and a modulation type used to modulate data in the interfering signal. The method further includes recovering the symbols from the desired signal using the information.

Abstract: One aspect of the present invention concerns the management of processing resource allocations for a Turbo receiver, where such resources are consumed from a finite resource budget within a defined processing time interval. The contemplated Turbo receiver attempts to allocate more processing resources to those demodulation and/or Turbo decoding tasks that make more valuable contributions with respect to the ultimate goal of successfully decoding all data streams that are of interest in a received signal. The advantageous management approach allows the Turbo receiver to obtain better results for a given consumption of processing resources, and further permits the Turbo receiver to quit upon either achieving a successful outcome within a defined processing time interval or exhausting the budgeted resources.

Abstract: A receiving device for receiving OFDM signals in which arrangement of pilot signals changes with symbol time, includes: an inverse Fourier transform unit configured to calculate an impulse response by performing an inverse Fourier transform on pilot signals included in a received signal; a first Doppler frequency estimation unit configured to estimate a first Doppler frequency from a phase rotation amount at peak positions between impulse responses of pilot signals of different subcarriers of the impulse responses; a second Doppler frequency estimation unit configured to estimate a second Doppler frequency from a phase rotation amount between impulse responses of pilot signals of the same subcarrier of the impulse responses; and a Doppler frequency selection unit configured to select one of the first and the second Doppler frequency estimated by the first and the second Doppler frequency estimation unit so as to reduce influence of a multipath.

Abstract: Methods, apparatus and computer programs are provided for performing signal interference ratio estimation with respect particularly to non-constant modulus data. A method is provided that includes causing one or more data symbols to be demodulated resulting in one or more soft bits. An estimate is determined for a second order moment and a fourth order moment for the one or more soft bits. A signal to noise ratio is determined based on a signal component and a noise component of the estimated second order moment and the estimated fourth order moment for the one or more soft bits.

Abstract: Aspects of the invention include methods and devices for inserting data and pilot symbols into Orthogonal Frequency Division Multiplexing (OFDM) frames having a time domain and a frequency domain. A method involves inserting in at least one zone of a first type a two dimensional array of data and pilot symbols in time and frequency and inserting in at least one zone of a second type a two dimensional array of data and pilot symbols in time and frequency. In some implementations the zone of the first type comprises common pilot symbols that can be detected by all receivers receiving the OFDM frame. In some implementations the zone of the second type comprises dedicated pilot symbols that are only detectable by a receiver that is aware of pre-processing used to encode the dedicated pilot symbols.

Abstract: A reception apparatus including: a receiver configured to receive a symbol including a plurality of bits and to calculate each of likelihoods for each of the plurality of bits, and a processor configured to quantize each of the likelihoods based on each of numbers of quantization bits for each of the plurality of bits, wherein all of the numbers of quantization bits are not same.

Abstract: A power adjusting method and apparatus provided by embodiments of the present invention relate to the field of communications. The power adjusting method of this embodiment includes: receiving a signal from a sending end, where the signal includes a cyclic prefix (CP) signal; detecting and acquiring first receiving power and second receiving power of the CP signal, where the first receiving power is average power of N sampling points of the CP signal, and the second receiving power is average power of M sampling points of the CP signal; after determining that a ratio of the first receiving power to target power is greater than a first preset threshold, adjusting signal power magnification; and after determining that the ratio of the second receiving power to the target power is greater than a second preset threshold, adjusting the signal power magnification again.

Abstract: Functionality can be implemented for automatic gain control (AGC) in a wireless network device to determine whether to change the gain of the wireless network device based on determining the strength of an RF signal. At various time instants, the strength of the RF signal can be compared against different thresholds to determine the presence of and severity of the saturation of the RF front end. The gain settings can be adjusted based on comparing the strength of the RF signal with a set of thresholds. This can help the wireless network device receive RF signals with little or no distortion, and can minimize RF saturation, gain compression, false detection and other performance degradation at the wireless network device.

Abstract: A communications method uses simultaneously at least two receivers to reduce a need for data retransmissions. When using multiple receivers it is enough that at least one of the receivers outputs a correct bit set which are preferably checked by Cyclic Redundancy Check (CRC). The method comprises the following to be performed in a radio modem: a) receiving the same sample of a signal in a first receiver and in a second receiver; and in response to the same sample b) obtaining a first bit set from the first receiver and a second bit set from the second receiver; and c) determining whether the first bit set or the second bit set is a correct bit set. A retransmission request is sent only when the first and second bit sets are erroneous. This reduces latencies in the transmission. One can change receivers depending on the radio frequency (RF) circumstances.

Abstract: An impulse noise mitigation circuit (INMC) may set a cut-off frequency of each of two high pass filters to bound a frequency bandwidth of a desired signal, wherein a first of the two filters allows frequencies higher than the frequency bandwidth of the desired signal, and a second of the two filters allows frequencies lower than the frequency bandwidth of the desired signal. The INMC may compute and store a mean magnitude separately for a first signal response of the first filter and a second signal response of the second filter. The INMC may select the first filter for impulse noise mitigation when the mean magnitude of the second filter is greater than the mean magnitude of the first filter. The INMC may select the second filter for impulse noise mitigation when the mean magnitude of the first filter is greater than the second filter.

Abstract: A system and a method for a commercial nuclear repository that turns heat and gamma radiation from spent nuclear fuel into a valuable revenue stream. Gamma radiation from the spent nuclear fuel of the repository may be used to irradiate and sterilize food and other substances. Gamma radiation may also be used to improve the properties of target substances. Additionally, heat decay from the spent nuclear fuel of the repository may be harnessed to heat materials or fluids. The heated fluids may be used, for instance, to produce steam that may make electricity. The heating of working fluids for use in processes, such as heated fluid streams for fermentation or industrial heating, may be transported out of the repository and co-mingled with other heat input, or other fluids.

Abstract: A method of collecting 3He from a nuclear reactor may include the steps of a) providing heavy water at least part of which is exposed to a neutron flux of the reactor, b) providing a cover gas in fluid communication with the heavy water, c) operating the nuclear reactor whereby thermal neutron activation of deuterium in the heavy water produces tritium (3H) and at least some of the tritium produces 3He gas by ?? decay and at least a portion of the 3He gas escapes from the heavy water and mixes with the cover gas, d) extracting an outlet gas stream, the outlet gas stream comprising a mixture of the cover gas and the 3He gas and e) separating the 3He gas from the outlet gas stream.

Abstract: A process for producing technetium-99m from a molybdenum-100 metal powder, comprising the steps of: (i) irradiating in a substantially oxygen-free environment, a hardened sintered target plate coated with a Mo-100 metal, with protons produced by a cyclotron; (ii) dissolving molybdenum ions and technetium ions from the irradiated target plate with an H2O2 solution to form an oxide solution; (iv) raising the pH of the oxide solution to about 14; (v) flowing the pH-adjusted oxide solution through a resin column to immobilize K[TcO4] ions thereon and to elute K2[MoO4] ions therefrom; (vi) eluting the bound K[TcO4] ions from the resin column; (vii) flowing the eluted K[TcO4] ions through an alumina column to immobilize K[TcO4] ions thereon; (viii) washing the immobilized K[TcO4] ions with water; (ix) eluting the immobilized K[TcO4] ions with a saline solution; and (x) recovering the eluted Na[TcO4] ions.

Abstract: Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.

Abstract: A nuclear power plant control system (1) includes a control button (21) which receives an operation for controlling a control target device (40), a notification lamp (12) which notifies that a control signal corresponding to the operation received by the control button (21) arrives at a predetermined position on a path connected from a control panel (20) to the control target device (40), and a control signal inhibition unit (33) which inhibits a control signal from arriving at the control target device (40) in midstream between the predetermined position on the path and the control target device (40) in response to an operation received by a test permission button (11).

Abstract: The object of the present invention is to provide a risk monitoring device and a risk monitoring method for use with a nuclear power facility, providing continuous determination of risk associated with the nuclear power facility, based on one-type security model, which can be implemented using simple software and hardware means.

Abstract: A method for controlling a nuclear reactor is disclosed. The method includes providing a moderator zone in a core of the nuclear reactor, providing a fuel in the moderator zone, and providing one or more housings, each having a cavity, adjacent to the fuel. The method also includes allowing movement of a moderator between the moderator zone and the cavity of the one or more housings at a lower portion of the one or more housings. The method further includes confining moderator in the cavity of the one or more housings at an upper portion of the one or more housings.

Abstract: Control rod drive mechanisms (CRDMs) include CRDM motors, and a support assembly provides bottom support of the CRDMs and includes a lateral alignment plate with openings receiving upper portions of the CRDMs. The upper portions of the CRDMs include compliance features engaging the openings of the lateral alignment plate. The compliance features may comprise angled leaf springs that wedge into the openings of the lateral alignment plate. In some embodiments the upper portion of each CRDM includes straps securing one or more cables to the upper portion of the CRDM, and the angled leaf springs are cut into or welded onto ends of the straps. Some embodiments further include a pressure vessel and a nuclear reactor core comprising fissile material disposed the pressure vessel, and the CRDM is an internal CRDM disposed in the pressure vessel along with the support assembly.

Abstract: An internal control rod drive mechanism (CRDM) including an electric motor is disposed in a nuclear reactor and further includes a support surface with sealed electrical connectors electrically connected with the electric motor power the motor. The internal CRDM is disposed on a support element secured inside the nuclear reactor. The support element includes sealed electrical connectors mating with the sealed electrical connectors on the support surface of the internal CRDM to power the electric motor. The sealed electrical connectors may be sealed glass, ceramic, or glass-ceramic connectors welded onto the ends of the MI cables extending from the motor. Springs, are disposed between the mating sealed electrical connectors of the support element and the support surface. A purge line is integrated with each mated connection.

Abstract: An integral pressurized water reactor (PWR) comprises: a cylindrical pressure vessel including an upper vessel section and a lower vessel section joined by a mid-flange; a cylindrical central riser disposed concentrically inside the cylindrical pressure vessel and including an upper riser section disposed in the upper vessel section and a lower riser section disposed in the lower vessel section; steam generators disposed inside the cylindrical pressure vessel in the upper vessel section; a reactor core comprising fissile material disposed inside the cylindrical pressure vessel in the lower vessel section; and control rod drive mechanism (CRDM) units disposed inside the cylindrical pressure vessel above the reactor core and in the lower vessel section. There is no vertical overlap between the steam generators and the CRDM units.

Abstract: A nuclear reactor includes a nuclear reactor core comprising fissile material and a pressure vessel containing the nuclear reactor immersed in primary coolant water at an operating pressure. The pressure vessel has a vessel penetration passing through a wall of the pressure vessel. An electrical feedthrough seals the vessel penetration and has an outside electrical connector mounted at the pressure vessel. The outside electrical connector is at atmospheric pressure. The electrical feedthrough may include a flange disposed inside the pressure vessel and sealing against an inside surface of the wall of the pressure vessel. The outside electrical connector of the electrical feedthrough may be inset into the wall of the pressure vessel.

Abstract: In a nuclear reactor, an internal control rod drive mechanism (CRDM) includes a motor and a hydraulically driven element connected by at least one hydraulic line with at least one hydraulic connector disposed on a mounting plate of the internal CRDM. A support element mounted in the nuclear reactor includes at least one hydraulic connector. The internal CRDM is supported on the support element by its mounting plate with each hydraulic connector of the internal CRDM mated with a corresponding hydraulic connector of the support element. The hydraulically driven element may be a piston controlling SCRAM, driven by coolant water, and the coolant water pressure in the at least one hydraulic line is higher than the coolant water pressure in the nuclear reactor. The mating of each hydraulic connector of the internal CRDM with a corresponding hydraulic connector of the support element may be a leaky mating that leaks coolant water into the pressure vessel.

Abstract: A nuclear reactor includes at least: a pressure vessel including an upper vessel section and a lower vessel section connected by a mid-flange and containing primary coolant; a nuclear reactor core disposed in the lower vessel section and immersed in the primary coolant; and upper internals suspended from the mid-flange of the pressure vessel. The upper internals include at least internal CRDMs immersed in the primary coolant and control rod guide frames. To refuel, the nuclear reactor is depressurized. The upper vessel section is disconnected and removed while leaving the mid-flange in place with the upper internals remaining suspended from the mid-flange. The mid-flange is then removed with the upper internals remaining suspended from the mid-flange. The fuel is replaced, the mid-flange is placed back onto the lower vessel section with the upper internals remaining suspended from the mid-flange, and the upper vessel section is placed back and re-connected.

Abstract: Fuel bundles for a nuclear reactor are described and illustrated, and in some cases include fuel elements each having a fissile content of 235U between about 0.9 wt % 235U and 5.0 wt % 235U, and wherein at least one of the fuel elements is a poisoned low-enriched uranium fuel element including a neutron poison in a concentration greater than about 5.0 vol %.

Abstract: A novel heat exchanger (FIG. 1) designed and fabricated based on dry ice-ethylene glycol (DIEG) bath 1 as the coolant mixture for the emergency core cooling system (ECCS) of the nuclear power systems to avoid core meltdown during the normal reactor shutdown or reactor scram in the emergency conditions. This method is proposed to upgrade the safety systems including modified ECCS which utilizes fast non-water coolant emergency system by fast cooling of reactor pressure vessel (RPV) 31 based on dry ice+ethylene glycol slurry 1.

Abstract: A nuclear reactor includes a nuclear reactor core disposed in a pressure vessel and immersed in primary coolant water at an operating pressure higher than atmospheric pressure. A containment structure contains the nuclear reactor. A reactor coolant inventory and purification system (RCI) is connected with the pressure vessel by make-up and letdown lines. The RCI includes a high pressure heat exchanger configured to operate responsive to a safety event at the operating pressure to remove heat from the primary coolant water in the pressure vessel. An auxiliary condenser located outside containment also removes heat. The RCI also includes a pump configured to inject make up water into the pressure vessel via the make-up line against the operating pressure. An emergency core cooling system (ECC) operates to depressurize the nuclear reactor only if the RCI and auxiliary condenser are unable to manage the safety event.

Abstract: A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.

Abstract: A pressure vessel comprises an upper vessel section and a lower vessel section. A nuclear reactor core comprises fissile material contained in a containing structure and disposed in the lower vessel section. Upper internals are disposed in the lower vessel section above the nuclear reactor core. The upper internals include at least guide frames and internal control rod drive mechanisms (CRDMs) with CRDM motors mounted on a suspended support assembly including a plurality of hanger plates connected by tie rods. The plurality of hanger plates includes a lowermost hanger plate having alignment features configured to align the upper internals with the containing structure that contains the nuclear reactor core.

Abstract: A pressure vessel comprises an upper vessel section and a lower vessel section. A nuclear reactor core comprising fissile material is disposed the lower vessel section. Upper internals are disposed in the lower vessel section above the nuclear reactor core and are mounted on a suspended support assembly including a plurality of hanger plates connected by tie rods. The upper internals include at least guide frames and internal control rod drive mechanisms (CRDMs) with CRDM motors. The plurality of hanger plates includes a mid-hanger plate that is not the uppermost plate of the plurality of hanger plates and is not the lowermost plate of the plurality of hanger plates. The internal CRDMs are disposed above the mid-hanger plate, the guide frames are disposed below the mid-hanger plate, and the mid-hanger plate engages both the internal CRDMs and the guide frames.

Abstract: A pressure vessel comprises an upper vessel section and a lower vessel section. A nuclear reactor core comprising fissile material is disposed in the lower vessel section. Upper internals are disposed in the lower vessel section above the nuclear reactor core. The upper internals include at least internal control rod drive mechanisms (CRDMs) with CRDM motors and a suspended support assembly with a plurality of hanger plates connected by tie rods. The internal CRDMs are supported from beneath by a first hanger plate and are laterally aligned by a second hanger plate disposed above the first hanger plate.

Abstract: A pressurized water reactor (PWR) includes a pressure vessel containing a nuclear core comprising a fissile material immersed in primary coolant water. A reactor coolant pump (RCP) is configured to pump primary coolant water in the pressure vessel. The RCP includes a hydraulically driven turbo pump disposed in the pressure vessel. The turbo pump includes an impeller performing pumping of primary coolant water in the pressure vessel, and a hydraulically driven turbine mechanically coupled with the impeller to drive the impeller. The RCP may further include a hydraulic pump configured pump primary coolant water to generate hydraulic working fluid that drives the hydraulically driven turbine. The hydraulic pump may be a canned pump having a casing defining a portion of the pressure boundary of the pressure vessel. The casing includes electrical feedthroughs delivering electrical power to the hydraulic pump.

Abstract: A nuclear reactor includes a nuclear core comprising a fissile material, and a pressure vessel containing the nuclear core immersed in primary coolant water. Turbo pumps disposed in the pressure vessel provide active circulation of primary coolant water in the pressure vessel. Each turbo pump includes a turbine driving an impeller. A manifold plenum chamber is disposed in the pressure vessel, and is in fluid communication with inlets of the turbines of the turbo pumps. An electrically driven pump operatively connected with the manifold plenum chamber to pressurize the manifold plenum chamber with primary coolant water. The turbo pumps may be disposed in openings passing through the manifold plenum chamber. The pressure vessel may be vertically oriented and cylindrical, with a cylindrical riser oriented coaxially inside, and the manifold plenum chamber may be annular and disposed in a downcomer annulus defined between the cylindrical riser and the cylindrical pressure vessel.

Abstract: A reactor coolant pump (RCP) generates primary coolant flow in a nuclear reactor. The RCP includes a flow amplification device, such as a turbo pump, disposed in the pressure vessel of the nuclear reactor, and an electrically driven pump (e.g. a centrifugal pump). The inlet of the electrically driven pump receives primary coolant water from the pressure vessel and the outlet discharges into the driving inlet of the flow amplification device (e.g. into the turbine of a turbo pump) such that the centrifugal pump drives the flow amplification device to pump primary coolant water. A divider is disposed in the pressure vessel and separates the pumping inlet of the flow amplification device from the pumping outlet of the flow amplification device. The electrically driven pump may include hydraulic drive shaft bearings and starting mechanical drive shaft bearings that disengage at operating speed due to axial shift of the drive shaft.

Abstract: An integral pressurized water reactor (PWR) includes a cylindrical pressure vessel, a cylindrical central riser disposed coaxially inside the cylindrical pressure vessel wherein a downcomer annulus is defined between the cylindrical central riser and the cylindrical pressure vessel, a nuclear core comprising a fissile material, and a steam generator disposed in the downcomer annulus. A reactor coolant pump (RCP) includes a jet pump disposed in the downcomer annulus above or below the steam generator, and a hydraulic pump configured to pump primary coolant into a nozzle of the jet pump. The hydraulic pump includes an electric motor mounted externally on the pressure vessel.

Abstract: A structural skeleton of a nuclear fuel assembly is assembled by inserting guide tubes through a plurality of spacer grids, and performing pulse arc welding to connect the inserted guide tubes and the spacer grids. In the structural skeleton, the spacer grids may comprise intersecting grid straps, and at least some of the grid straps may include tabs that are pulse arc welded to guide tubes. The structural skeleton may include grid retaining rings installed on the guide tubes and pinning some spacer grids, with the grid retaining rings being pulse arc welded to guide tubes. A fuel assembly includes the structural skeleton, a plurality of fuel rods comprising fissile material passing through the spacer grids, and upper and lower end fittings secured to upper and lower ends, respectively, of the guide tubes.

Abstract: A shift register is discussed in which a pull-up switching device is turned off positively in a period in which no scan pulse is forwarded for securing drive stability and prevents a picture quality from becoming poor. The shift register in one embodiment includes stages having any one of first and second start pulses, and any one of first to fourth clock pulses to forward a scan pulse in succession, wherein the first and second start pulses are in gate high voltage states for two horizontal periods, with the second start pulse forwarded with a delay of one horizontal period than the first start pulse. The first to fourth clock pulses are in gate high voltages for two horizontal periods, with one horizontal period delay to one another.

Abstract: An object is to enhance the driving capability and improve the operating speed of a unit shift register applicable to a scanning line driving circuit having a partial display function. A unit shift register forming a gate line driving circuit includes a first transistor that supplies a first clock signal to a first output terminal, a second transistor that supplies a second clock signal to a second output terminal, a third transistor that charges the gate of the first transistor in response to activation of a shift signal of the previous stage, and a fourth transistor connected between the gate of the first transistor and the gate of the second transistor. The first clock signal and the second clock signal have the same phase, and only the second clock signal is activated in a particular period (a display ineffective period).

Abstract: A method and a system are provided to prepare a plurality of cuttings or other rock fragments or other porous media, such as cuttings from a drilling interval or multiple intervals, for computer tomographic scanning at the same time. A method and system also are provided to allow organization of mass quantities of cuttings or other rock fragments obtained from intervals of a well to more accurately categorize the cuttings to assist selections thereof for more detailed digital rock analysis, such as using SEM and FIB-SEM systems, are provided. A method and system also are provided to allow characterization of facies occurrence frequency of a depth interval using drill cuttings or other rock fragments. Computerized systems, computer readable media, and programs for performing the methods are also provided.

Abstract: An analysis method for use in a radiation imaging apparatus employing intensity information of interference fringes of radiation rays that have passed through a detected object includes the steps of generating first phase information of the detected object wrapped into a range of 2? from the intensity information of the interference fringes; generating information on an absorption intensity gradient of the detected object from the intensity information of the interference fringes; generating a weighting function on the basis of an absolute value of a gradient in the information on the absorption intensity gradient; and generating second phase information by unwrapping the first phase information by using the weighting function.

Abstract: The present invention relates to a photographing device including a power transmission unit. The power transmission unit includes a frame unit which is connected to the second drive body, an adaptor unit which is connected to the frame unit and is selectively connected to the first drive body or the support body by external power, an actuating unit which operates the adaptor unit, and a power unit which transmits power to the actuating unit. According to the power transmission unit of the X-ray mammography device, since biopsy photography and tomography can be performed using only one power transmission unit, the weight and size of the rotating arm may be reduced, and the vibration and noise produced thereby may be reduced. Thanks to the simple operation mechanism of the power transmission unit, power loss may be reduced, and the durability of each component may be improved.

Abstract: A radiation control system and method are provided in which radiation delivered to a patient and/or the operator of the equipment is minimized. The radiation control system may be used in a large variety of applications including applications in which radiation source is used to inspect an object, such as, for example, medical imaging, diagnosis and therapy, in manufacturing operation using radiation, in airports scanning systems, in different security setups, and in nuclear reactors automation and process control. The radiation control system and method may also be used with 3D imaging.

Abstract: A calibration method of a radiation detecting apparatus, a control method of a radiation imaging apparatus and a radiation imaging apparatus are provided. The control method of the radiation imaging apparatus includes performing prior information acquisition by obtaining at least one correction threshold energy, at which a theoretical radiation intensity of at least one threshold energy is measured, and performing radiation image acquisition by obtaining at least one radiation image at the at least one threshold energy using the at least one correction threshold energy.