Abstract: A method for detecting an artifact of a blood pressure signal includes measuring consecutive signals of blood pressure in real time, dividing the consecutive signals into a plurality of unit waveforms by searching systolic starting points and peak points from the measured signals, determining two outputs by applying N consecutive unit waveforms among the plurality of unit waveforms as an input to a deep belief network (DBN), and determining whether the signal is an artifact or a normal signal by using the two determined outputs. According to the present disclosure, it is possible to minimize various false alarms of bio-signal streams which are measured in real time by automatically eliminating ABP artifacts using a deep belief network (DBN) which is one of deep neural network (DNN) models capable of learning causes and shapes of various types of artifacts together.

Abstract: A method of a nuclear fuel pellet including a thermal conductive metal and a nuclear fuel pellet prepared thereby. The method includes preparing an oxide nuclear fuel granule having about 30%-45% theoretical density, mixing the fuel granule with thermal conductive metal powder, compacting the fuel granule with which the thermal conductive metal powder is mixed to prepare a green pellet, and sintering the green pellet. In the method, the sintering may be performed under a reducing gas atmosphere that is the same as the commercial pellet preparing process. Thus, compatibility compared to existing commercial preparing processes may be superior. Also, since a liquefied oxide formation process and a reducing process are omitted, the distribution uniformity of the metal material within the pellet may be superior. Therefore, the nuclear fuel pellet in which the metal network and fine microstructure are uniformly distributed within the pellet may be prepared.

Abstract: A uranium dioxide nuclear fuel pellet has about 50 to about 400 ?M (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.

Abstract: The present invention relates to a device and a method for detecting a feature of an arterial blood pressure (ABP) waveform. The feature detecting method of an ABP waveform according to an exemplary embodiment of the present invention includes: searching a peak and a trough; detecting a systolic peak based on a time interval between a peak and a neighboring peak and an average pressure value; detecting a pulse onset with respect to a trough directly before the systolic peak; extracting a candidate of a dicrotic notch based on a magnitude of the systolic peak and a measurement time; detecting a point having a lowest pressure value among candidates of the dicrotic notch as a dicrotic notch and detecting a dicrotic peak based on the dicrotic notch; and classifying the detected dicrotic notches into a normal notch and a transient notch.

Abstract: The present invention relates to a device and a method for detecting a peak of an intracranial pressure (ICP) waveform using a morphological feature of an arterial blood pressure waveform.

Abstract: A method for eliminating an artifact of a computed tomography image is provided. The method includes eliminating a machine artifact from a cross-sectional computed tomography scans of the brain; setting boundary points positioned on a horizontal axis and a vertical axis in the computed tomography image, from which the machine artifact has been eliminated; resetting a boundary point positioned at a boundary between the skull of the brain and the brain tissue based on the boundary points; detecting a position of a fracture of the brain in the computed tomography image, in which the boundary point has been reset, and overlaying a fracture region with a skull pixel; and eliminating an artifact from the computed tomography image, which has been overlaid with the skull pixel.

Abstract: A method for densitometric analysis of a computed tomography image is provided. The method includes converting CT numbers of each pixel of a cross-sectional computed tomography image of the brain into Hounsfield unit (HU) values; eliminating an artifact from the computed tomography image of which the CT numbers of each pixel have been converted into the HU values, and extracting the brain tissues; and extracting a density distribution of the HU values from the computed tomography image, in which the artifact has been removed and the brain tissues have been extracted.

Abstract: Disclosed is a uranium dioxide nuclear fuel pellet, which includes metallic microcell partitions having a high protection capacity for fission products and a high thermal conductivity simultaneously. These metal microcell partitions are arranged in the nuclear fuel pellet to trap fission products. Further disclosed is a method of making the uranium dioxide nuclear fuel pellet. The method includes providing a mixture of uranium dioxide powder and additive powder of Cr-containing compound or Mo-containing compound; compressing the powder mixture to form a green pellet; and then sintering the green pellet under reducing gas environment to form the metallic microcell partitions.

Abstract: A fabrication method of burnable absorber nuclear fuel pellets and burnable absorber nuclear fuel pellets fabricated by the same are provided, in which the fabrication method includes adding boron compound and manganese compound to one or more type of nuclear fuel powders selected from the group consisting of uranium dioxide (UO2), plutonium dioxide (PuO2) and thorium dioxide (ThO2) and mixing the same (step 1), compacting the mixed powder of step 1 into compacts (step 2), and sintering the compacts of step 2 under hydrogen atmosphere (step 3). According to the fabrication method, sintering can be performed under hydrogen atmosphere at a temperature lower than the hydrogen atmosphere sintering that is conventionally applied in the nuclear fuel sintered pellet mass production, by adding sintering additives such as manganese oxide or the like.

Abstract: A method of a nuclear fuel pellet including a thermal conductive metal and a nuclear fuel pellet prepared thereby. The method includes preparing an oxide nuclear fuel granule having about 30%-45% theoretical density, mixing the fuel granule with thermal conductive metal powder, compacting the fuel granule with which the thermal conductive metal powder is mixed to prepare a green pellet, and sintering the green pellet. In the method, the sintering may be performed under a reducing gas atmosphere that is the same as the commercial pellet preparing process. Thus, compatibility compared to existing commercial preparing processes may be superior. Also, since a liquefied oxide formation process and a reducing process are omitted, the distribution uniformity of the metal material within the pellet may be superior. Therefore, the nuclear fuel pellet in which the metal network and fine microstructure are uniformly distributed within the pellet may be prepared.

Abstract: A method for densitometric analysis of a computed tomography image is provided. The method includes converting CT numbers of each pixel of a cross-sectional computed tomography image of the brain into Hounsfield unit (HU) values; eliminating an artifact from the computed tomography image of which the CT numbers of each pixel have been converted into the HU values, and extracting the brain tissues; and extracting a density distribution of the HU values from the computed tomography image, in which the artifact has been removed and the brain tissues have been extracted.

Abstract: A method for eliminating an artifact of a computed tomography image is provided. The method includes eliminating a machine artifact from a cross-sectional computed tomography scans of the brain; setting boundary points positioned on a horizontal axis and a vertical axis in the computed tomography image, from which the machine artifact has been eliminated; resetting a boundary point positioned at a boundary between the skull of the brain and the brain tissue based on the boundary points; detecting a position of a fracture of the brain in the computed tomography image, in which the boundary point has been reset, and overlaying a fracture region with a skull pixel; and eliminating an artifact from the computed tomography image, which has been overlaid with the skull pixel.

Abstract: Provided are a method of controlling the compositional gradient and solubility of doped-additives at grain boundaries during sintering of a uranium-based oxide green pellet including the additives, and a method of manufacturing a sintered nuclear fuel pellet having a large grain size using the same. The grain boundary solubility of the doped-additives is maintained at a certain level by stepwise varying of an oxygen partial pressure during isothermal sintering of a uranium-based oxide green pellet including the additives. The method of manufacturing a sintered nuclear fuel pellet having a large grain size includes preparing additive mixed uranium oxide powder, forming an additive mixed uranium oxide green pellet using the mixed powder, heating the green pellet to a sintering temperature in a gas atmosphere having a low oxygen partial pressure, and sintering while a sintering gas atmosphere is changed to stepwise increase an oxygen partial pressure at the isothermal sintering temperature.

Abstract: A uranium dioxide nuclear fuel pellet has about 50 to about 400 ?M (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.

Abstract: A uranium dioxide nuclear fuel pellet includes metallic microcells having a high protection capacity for fission products and a high thermal conductivity simultaneously arranged in the nuclear fuel pellet to trap fission products, such that extraction of fission products may be restrained in a normal operation condition and that the temperature of a nuclear fuel may be lowered to enhance the performance of the nuclear fuel, only to restrain extraction of radioactive fission products toward the environment in an accident condition to enhance a stability of the nuclear fuel pellet, and a fabricating method thereof.

Abstract: A method for fabricating a sintered annular nuclear fuel pellet includes molding nuclear fuel powder or granule, an oxide of a fissile element (M), to fabricate an annular nuclear fuel green body. A rod-like shaped structure is inserted into the annular nuclear fuel green body and sintered in a slight oxidizing gas atmosphere such that the oxide of the fissile element has a balanced O/M ratio higher than a desired O/M ratio (oxygen/fissile element) of a final sintered annular nuclear fuel pellet, while being maintained in a cubic phase. The sintered annular nuclear fuel pellet is then reduced in a reductive gas atmosphere so as to have the desired O/M ratio in the state that the rod-like shaped structure is inserted.

Abstract: A method for fabricating a sintered annular nuclear fuel pellet includes: molding nuclear fuel powder or granules to fabricate an annular nuclear fuel green body; inserting a rod-like shaped structure into the annular nuclear fuel green body; sintering the rod-like shaped structure-inserted annular nuclear fuel green body in a reductive gas atmosphere; and separating the sintered annular nuclear fuel pellet from the rod-like shaped structure.

Abstract: Provided is an apparatus for inputting a character which enables users to input characters more conveniently by arranging input keys having 3 or 4 input interfaces appropriately in a keypad. If the present invention is applied to small sized electronic equipment such as a mobile phone and PDA, much more various types of characters can be arranged as compared with the space the input keys take, and thereby it becomes possible to input characters faster with the minimum amount of effort.

Abstract: A method for manufacturing an annular nuclear fuel pellet is provided. In the method, an annular nuclear fuel green compact whose lateral cross-section is a trapezoid is prepared. The thickness of the annular nuclear fuel green compact reduces along one direction of the central axis, and a green density of the nuclear fuel green compact increases along one direction of the central axis. The annular nuclear fuel green compact is sintered under a reducing gas atmosphere so that the annular nuclear fuel pellet is obtained. According to this method, the annular pellet which has uniform inner and outer diameters and small diametric tolerances along the pellet height is fabricated without grinding the pellet surfaces.

Abstract: Provided are a method of controlling the compositional gradient and solubility of doped-additives at grain boundaries during sintering of a uranium-based oxide green pellet including the additives, and a method of manufacturing a sintered nuclear fuel pellet having a large grain size using the same. The grain boundary solubility of the doped-additives is maintained at a certain level by stepwise varying of an oxygen partial pressure during isothermal sintering of a uranium-based oxide green pellet including the additives. The method of manufacturing a sintered nuclear fuel pellet having a large grain size includes preparing additive mixed uranium oxide powder, forming an additive mixed uranium oxide green pellet using the mixed powder, heating the green pellet to a sintering temperature in a gas atmosphere having a low oxygen partial pressure, and sintering while a sintering gas atmosphere is changed to stepwise increase an oxygen partial pressure at the isothermal sintering temperature.