Abstract: Provided are: an optical laminate comprising a second adhesive layer, a second adhesive layer laminated on the second adhesive layer, and a light shield part laminated between the first adhesive layer and the second adhesive layer; an optical member comprising same; and an optical display device including same.

Abstract: A multi-machine and performance based continuous production planning global optimization scheduling method and device are disclosed. The device for multi-machine and performance-based continuous production planning global optimization scheduling may include a data pre-processing module configured to generate a multi-machine list on performable multiple machines through pre-processing scheduling target data, a scheduling module configured to generate a scheduling result by setting a processing time for a machine related to a single machine list, wherein the single machine list is selected from the multi-machine list, and a data post-processing module configured to store the scheduling result in a database.

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.