Abstract: Proposed is a detachable mooring system for an offshore structure, including a first tension adjuster connected to an offshore structure, and blocking a pulling chain from proceeding from an outlet of a body toward an inlet, a second tension adjuster connected to one end of the pulling chain and blocking the pulling chain from proceeding from an outlet of a body toward an inlet, a mooring chain having a first longitudinal end connected to one surface of the second tension adjuster body and having a second longitudinal end connected to an anchor on the seabed, a first lead rope having one longitudinal end connected to one end of the pulling chain discharged out through the first tension adjuster outlet, and a second lead rope having one longitudinal end connected to the second tension adjuster body.

Abstract: A vehicle body structure includes a roof side assembly connecting upper end portions of pillars of a vehicle body in a longitudinal direction of the vehicle body, the roof side assembly forming an A-pillar itself, a mounting bracket fixing the roof side assembly to a lower vehicle body, and an external garnish coupled to an outside of the roof side assembly, wherein the roof side assembly includes a pipe extending in the longitudinal direction of the vehicle body, the pipe including a closed cross-section, and a molding member injection-molded with the pipe inserted thereinto.

Abstract: A radio frequency (RF) weak magnetic field detection sensor includes a ferromagnetic core, a pickup coil disposed to surround the ferromagnetic core, a substrate that includes an opening, a core pad connected to the ferromagnetic core and a coil pad connected to the pickup coil, and an insulating tube interposed between the ferromagnetic core and the pickup coil. The insulating tube includes a bobbin around which the pickup coil is wound, and a core hole formed to pass through the bobbin and configured to accommodate the ferromagnetic core.

Abstract: A memory device includes gate electrode layers stacked on an upper surface of a substrate and each including a plurality of unit electrodes extending in a first direction, and a plurality of connecting electrodes connecting the unit electrodes to each other. The memory device also includes channel structures extending through the gate electrode layers in a direction perpendicular to the upper surface of the substrate, first common source lines extending in the first direction and interposed between the unit electrodes, and second common source lines extending in the first direction between the first common source lines and each having a first line and a second line separated from each other in the first direction by the connecting electrodes.

Abstract: A vehicle body structure includes a roof side assembly connecting upper end portions of all pillars of a vehicle body along a front and rear direction of the vehicle body and forming an A-pillar itself; a plurality of brackets for fixing the roof side assembly to a lower vehicle body; and an external garnish coupled to an external side of the roof side assembly.

Abstract: An apparatus and method for treating a substrate are provided. The apparatus includes at least one first process chamber configured to supply a developer onto the substrate; at least one second process chamber configured to treat the substrate using a supercritical fluid; a transfer chamber configured to transfer the substrate from the at least one first process chamber to the at least one second process chamber, while the developer supplied in the at least one first process chamber remains on the substrate; and a temperature and humidity control system configured to manage temperature and humidity of the transfer chamber by supplying a first gas of constant temperature and humidity into the transfer chamber.

Abstract: An apparatus and method for transmitting and receiving magnetic field signals in a magnetic field communication system are provided. The apparatus includes a controller configured to generate a communication signal, matching units that are configured to receive the communication signal and that respectively correspond to different matching frequencies, and loop antennas that are connected to the matching units, respectively, and that are configured to convert communication signals according to the different matching frequencies into magnetic transmission signals in the form of magnetic field energy and to transmit the magnetic transmission signals.

Abstract: Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same. An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use. Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage.

Abstract: Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same. An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use. Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage.

Abstract: Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same. An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use. Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage.

Abstract: A method of preparing a simple ceramic ingot of a spent filter having radioactive cesium trapped therein, and a ceramic ingot of a spent filter having improved properties such as leach resistance, thermal stability, and cesium content are provided. The method includes grinding and mixing a spent filter having cesium trapped therein, adding a solidifying agent, and sintering the spent filter. The method of preparing a ceramic ingot of a spent filter can be useful in preparing the ceramic ingot of the spent filter from only the spent filter by means of simple grinding and sintering, and in preparing the ceramic ingot of the spent filter by adding a small amount of a solidifying agent. The ceramic ingot of the spent filter has a high density and improved thermal stability, and shows improved leach resistance since a leach rate of a radioactive material is remarkably low. Therefore, the spent filter having radioactive cesium trapped therein can be effectively used to prepare a stable ceramic ingot.

Abstract: A method of preparing a simple ceramic ingot of a spent filter having radioactive cesium trapped therein, and a ceramic ingot of a spent filter having improved properties such as leach resistance, thermal stability, and cesium content are provided. The method includes grinding and mixing a spent filter having cesium trapped therein, adding a solidifying agent, and sintering the spent filter. The method of preparing a ceramic ingot of a spent filter can be useful in preparing the ceramic ingot of the spent filter from only the spent filter by means of simple grinding and sintering, and in preparing the ceramic ingot of the spent filter by adding a small amount of a solidifying agent. The ceramic ingot of the spent filter has a high density and improved thermal stability, and shows improved leach resistance since a leach rate of a radioactive material is remarkably low. Therefore, the spent filter having radioactive cesium trapped therein can be effectively used to prepare a stable ceramic ingot.

Abstract: A filter type trapping agent for volatile cesium compound and trapping method for volatile cesium compound thereof are provided. More particularly, a filter type trapping agent for volatile cesium compound including silica 40-65% by weight of silica, 15-30% by weight of alumina, 5-15% by weight of iron oxide, 1-15% by weight of molybdenum oxide, 1-10% by weight of chromium oxide, and 1-10% by weight of vanadium oxide and trapping method for volatile cesium compound thereof are provided. Through a filter type trapping agent for volatile cesium compound and a trapping method, only cesium can be selectively separated among the nuclear fission gases. Accordingly, by disposing only the filter where cesium is trapped, the efficiency of an off-gas process improves, expense for disposing filter wastes decreases, and a cesium isotope of the waste filter can be recycled. Therefore, many forms of cesium compound gas are made insoluble efficiently.

Abstract: A filter type trapping agent for volatile cesium compound and trapping method for volatile cesium compound thereof are provided. More particularly, a filter type trapping agent for volatile cesium compound including silica 40˜65% by weight of silica, 15˜30% by weight of alumina, 5˜15% by weight of iron oxide, 1˜15% by weight of molybdenum oxide, 1˜10% by weight of chromium oxide, and 1˜10% by weight of vanadium oxide and trapping method for volatile cesium compound thereof are provided. Through a filter type trapping agent for volatile cesium compound and a trapping method, only cesium can be selectively separated among the nuclear fission gases. Accordingly, by disposing only the filter where cesium is trapped, the efficiency of an off-gas process improves, expense for disposing filter wastes decreases, and a cesium isotope of the waste filter can be recycled. Therefore, many forms of cesium compound gas are made insoluble efficiently.

Abstract: A remote-controlled mobile cleaning device for removal and collection of high radioactive waste debris in a spent nuclear fuel process and fabrication area, such as a hot-cell, is disclosed. The device includes navigation means for moving it to the desired cleaning location and climbing over such obstacles as electrical cables and pneumatic tubes placed on the hot-cell floor to be cleaned, suction and collection means for dislodging, filtering, and capturing high radioactive waste debris, and cover means for protecting suction and collection means. The device that is operated by remote control cleans and collects loose dry spent nuclear fuel powder and other high-radioactive waste debris adhered to both the contaminated in-cell floor and the in-cell spent nuclear fuel process and fabrication equipment, without spreading inside the hot-cell.

Abstract: A remote-controlled mobile cleaning device for removal and collection of high radioactive waste debris in a spent nuclear fuel process and fabrication area, such as a hot-cell, is disclosed. The device includes navigation means for moving it to the desired cleaning location and climbing over such obstacles as electrical cables and pneumatic tubes placed on the hotcell floor to be cleaned, suction and collection means for dislodging, filtering, and capturing high radioactive waste debris, and cover means for protecting suction and collection means. The device that is operated by remote control cleans and collects loose dry spent nuclear fuel powder and other high-radioactive waste debris adhered to both the contaminated in-cell floor and the in-cell spent nuclear fuel process and fabrication equipment, without spreading inside the hot-cell.

Abstract: The invention discloses a method for treating a heavy metal containing waste water by using acorns. Acorns and nuts of other trees belonging to the Eagaceae group are dried at the room temperature and under the sun beams. Then acornic acid is extracted from the dried acorns. Then the acornic acid is filtered until it becomes colorless. A heavy metal containing waste water (low concentration and high concentration) is maintained at pH=8-11.5 by adding NH.sub.4 OH, Ca(OH).sub.2 and NAOH. Then the acornic acid is added into the waste water, and then, Ca.sup.++ ions singly or together with other divalent cations are added by 50 ppm. Then this solution is agitated for several minutes, and then, the heavy metals are precipitated, or the solution is filtered, thereby treating the heavy metal containing waste water.