Abstract: Disclosed is a positive electrode material for a lithium secondary battery. The positive electrode material includes a positive electrode active material formed of Li—[Mn—Ti]-M-O-based material including a transition metal (M) to enable reversible intercalation and deintercalation of lithium and molybdenum oxide. The positive electrode active material is coated with the molybdenum oxide to form a coating layer on a surface thereof.

Abstract: An altitude and azimuth angle concurrent driving type solar tracking apparatus, which includes: a worm receiving rotational power through a first end and coupled to a central shaft in a casing; an altitude actuator engaged with the worm; an azimuth actuator engaged with the worm; a diurnal motion control frame composed of a first azimuth link arm and a second azimuth link arm; a meridian altitude angle control frame composed of a first altitude link arm, a second altitude link arm, and an altitude actuating arm; and a solar panel mount coupled to a second end of the second azimuth link arm. The apparatus simultaneously tracks the altitude angle and the azimuth angle of the sun using rotational power transmitted through the first end of the worm and maintains the base of a solar panel parallel to the ground when tracking the sun.

Abstract: An altitude and azimuth angle concurrent driving type solar tracking apparatus, which includes: a worm receiving rotational power through a first end and coupled to a central shaft in a casing; an altitude actuator engaged with the worm; an azimuth actuator engaged with the worm; a diurnal motion control frame composed of a first azimuth link arm and a second azimuth link arm; a meridian altitude angle control frame composed of a first altitude link arm, a second altitude link arm, and an altitude actuating arm; and a solar panel mount coupled to a second end of the second azimuth link arm. The apparatus simultaneously tracks the altitude angle and the azimuth angle of the sun using rotational power transmitted through the first end of the worm and maintains the base of a solar panel parallel to the ground when tracking the sun.

Abstract: Disclosed herein is a method for manufacturing oxide fuel pellets. The method for manufacturing the oxide fuel pellets includes (step 1) preparing nuclear fuel powder containing uranium dioxide (UO2+x, x=0 to 0.20), (step 2) compacting the nuclear fuel powder prepared in step 1 to manufacture green pellets, sintering the green pellets manufactured in step 2 at a temperature of about 1,200° C. to about 1,400° C. by using an atmosphere gas, and reducing the green pellets sintered in step 3 at a temperature of about 800° C. to about 1,000° C. by using a reducing atmosphere gas. The method for manufacturing the oxide fuel pellets according to the present invention performs the sintering at a low temperature of about 1,200° C. to 1,400° C. to manufacture economical and safe oxide fuel pellets that are adequate for the nuclear fuel specification.

Abstract: A method for fabricating porous UO2 sintered pellets to be fed into the electrolytic reduction process for the purpose of metallic nuclear fuel recovery is provided, which includes forming a powder containing U3O8 by oxidizing spent nuclear fuel containing uranium dioxide (UO2) (step 1), fabricating green pellets by compacting the powder formed in step 1 (step 2), fabricating UO2+x sintered pellets by sintering the porous U3O8 green pellets fabricated in step 2 at 1200 to 1600° C., in an atmospheric gas (step 3), and forming UO2 sintered pellets by cooling the UO2+x sintered pellets to room temperature, and reduction the same at 1000 to 1400° C., in a reducing atmosphere (step 4).

Abstract: The present invention relates to a novel isolated gene (polynucleotide) which encodes a protein having a biofilm formation inhibitory activity derived from Coryneform bacteria, a L-lysine-producing strain in which the polynucleotide is inactivated, and a method for producing L-lysine using the same.

Abstract: Disclosed herein is a method for manufacturing oxide fuel pellets. The method for manufacturing the oxide fuel pellets includes (step 1) preparing nuclear fuel powder containing uranium dioxide (UO2+x, x=0 to 0.20), (step 2) compacting the nuclear fuel powder prepared in step 1 to manufacture green pellets, sintering the green pellets manufactured in step 2 at a temperature of about 1,200° C. to about 1,400° C. by using an atmosphere gas, and reducing the green pellets sintered in step 3 at a temperature of about 800° C. to about 1,000° C. by using a reducing atmosphere gas. The method for manufacturing the oxide fuel pellets according to the present invention performs the sintering at a low temperature of about 1,200° C. to 1,400° C. to manufacture economical and safe oxide fuel pellets that are adequate for the nuclear fuel specification.

Abstract: The present invention relates to a novel isolated gene (polynucleotide) which encodes a protein having a biofilm formation inhibitory activity derived from Coryneform bacteria, a L-lysine-producing strain in which the polynucleotide is inactivated, and a method for producing L-lysine using the same.

Abstract: A radiation detecting device is provided, according to which it is possible use only one radiation detecting device to measure radiation and measure gamma ray and neutron at once and discriminately in a restricted space. The radiation detecting device includes a radiation detecting unit to measure gamma ray and neutron discriminately at once, and a signal processing circuit which applies voltage to the neutron detecting unit and indicates measured gamma ray and neutron discriminately.

Abstract: A radiation detecting device is provided, according to which it is possible use only one radiation detecting device to measure radiation and measure gamma ray and neutron at once and discriminately in a restricted space. The radiation detecting device includes a radiation detecting unit to measure gamma ray and neutron discriminately at once, and a signal processing circuit which applies voltage to the neutron detecting unit and indicates measured gamma ray and neutron discriminately.

Abstract: The present invention relates to a well type neutron counter containing a He-3 detector which includes at least one annular gas layer in a polyethylene moderator, which includes a body formed of a neutron moderator and having a sample cavity for inserting a sample of nuclear material therein; and an annular He-3 detector tube including at least one annular gas layer into which at least He-4 or He-3 gas or their mixture is injected and a plurality of anode rods stood in the annular gas layer with an equal spaces, wherein the He-3 detector tube is formed in an inside of the body so as to surround the sample cavity. The neutron counter has a largely reduced size, simplified structure and resultant decreased failure rate as compared to a conventional counter with a large volume.

Abstract: The present invention relates to a well type neutron counter containing a He-3 detector which includes at least one annular gas layer in a polyethylene moderator, which includes a body formed of a neutron moderator and having a sample cavity for inserting a sample of nuclear material therein; and an annular He-3 detector tube including at least one annular gas layer into which at least He-4 or He-3 gas or their mixture is injected and a plurality of anode rods stood in the annular gas layer with an equal spaces, wherein the He-3 detector tube is formed in an inside of the body so as to surround the sample cavity. The neutron counter has a largely reduced size, simplified structure and resultant decreased failure rate as compared to a conventional counter with a large volume.