公开(公告)号：US09087618B2

公开(公告)日：2015-07-21

申请号：US13334941

申请日：2011-12-22

申请人： Hwan Seo Park ,  Byung-Gil Ahn ,  Hwan-Young Kim ,  In-Tae Kim ,  Yung-Zun Cho ,  Hansoo Lee

发明人： Hwan Seo Park ,  Byung-Gil Ahn ,  Hwan-Young Kim ,  In-Tae Kim ,  Yung-Zun Cho ,  Hansoo Lee

IPC分类号： G21F9/30 ,  C02F1/76

CPC分类号： G21F9/30 ,  C02F1/76 ,  G21F9/305

摘要： The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability.

摘要翻译： 本发明涉及一种用于固化伴随氯再循环或放射性碘去除的放射性废物的方法和装置。 本发明提供了一种用于通过包括破碎，混合/脱卤和烧结在内的固化系统在高温下高挥发性金属卤化物处理放射性废物的方法和装置。 在本发明的放射性废物固化方法和装置中，通过使用控制反应器表面的温度的方法，在氧化性气氛下对高腐蚀性金属盐进行脱卤材料的脱氯工序，进行固化 通过除去放射性碘，同时重复使用废气中所含的氯。 因此，可以减少所产生的总废物量，因此本发明的方法和装置可有效地用于制备具有高耐久性的凝固体。

公开(公告)号：US20120165594A1

公开(公告)日：2012-06-28

申请号：US13334941

申请日：2011-12-22

申请人： Hwan Seo PARK ,  Byung-Gil Ahn ,  Hwan-Young Kim ,  In-Tae Kim ,  Yung-Zun Cho ,  Hansoo Lee

发明人： Hwan Seo PARK ,  Byung-Gil Ahn ,  Hwan-Young Kim ,  In-Tae Kim ,  Yung-Zun Cho ,  Hansoo Lee

IPC分类号： G21F9/28

CPC分类号： G21F9/30 ,  C02F1/76 ,  G21F9/305

摘要： The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability.

摘要翻译： 本发明涉及一种用于固化伴随氯再循环或放射性碘去除的放射性废物的方法和装置。 本发明提供了一种用于通过包括破碎，混合/脱卤和烧结在内的固化系统在高温下高挥发性金属卤化物处理放射性废物的方法和装置。 在本发明的固体放射性废物的方法和装置中，通过使用控制反应器表面温度的方法，在氧化性气氛下对高腐蚀性金属盐进行脱卤材料的脱氯处理，进行凝固 通过除去放射性碘，同时重复使用废气中所含的氯。 因此，可以减少所产生的总废物量，因此本发明的方法和装置可有效地用于制备具有高耐久性的凝固体。

公开(公告)号：US20090005628A1

公开(公告)日：2009-01-01

申请号：US12216014

申请日：2008-06-27

申请人： Yung-Zun Cho ,  Hee-Chul Yang ,  Hee-Chul Eun ,  In-Tae Kim ,  Han-Soo Lee ,  Hwan-Seo Park

发明人： Yung-Zun Cho ,  Hee-Chul Yang ,  Hee-Chul Eun ,  In-Tae Kim ,  Han-Soo Lee ,  Hwan-Seo Park

IPC分类号： G21F9/00 ,  B01J19/00

CPC分类号： C25C3/34 ,  G21F9/06

摘要： A reuse apparatus of eutectic salt waste produced in an electro refining process and a method thereof is a technology that in order to collect the eutectic salt of the eutectic salt waste, oxidizes/precipitates nuclides (rare earth and TRU) within the eutectic salt waste, an oxygen dispersing method is used to perform a layer separation into the eutectic salt layer and the precipitate layer. Then, the precipitate layer and eutectic salt layer are separated and collected, so that the eutectic salt layer is directly reused and the eutectic salt within the precipitates is reused by separating and collecting it using distillation/condensation processes. The reuse apparatus of the eutectic salt waste and a method thereof thereby increases the collecting efficiency of the eutectic salt and allows the compositions of the collected eutectic salt to have the same compositions as the eutectic salt used in the electro refining process.

摘要翻译： 在电精炼工艺中生产的共晶盐水废弃物的再利用装置及其方法是为了收集共晶盐废物的共晶盐，在共晶盐废物内氧化/沉淀出核素（稀土和TRU） 使用氧分散法进行到共晶盐层和沉淀层的层分离。 然后，分离收集沉淀层和共晶盐层，使共晶盐层直接再利用，沉淀中的共晶盐通过使用蒸馏/缩合方法分离和收集而再利用。 共晶盐矿废弃物的再利用装置及其方法因此提高了共晶盐的收集效率，并且允许收集的共晶盐的组成与用于电精炼过程的共晶盐具有相同的组成。

公开(公告)号：US07875760B2

公开(公告)日：2011-01-25

申请号：US12216014

申请日：2008-06-27

申请人： Yung-Zun Cho ,  Hee-Chul Yang ,  Hee-Chul Eun ,  In-Tae Kim ,  Han-Soo Lee ,  Hwan-Seo Park

发明人： Yung-Zun Cho ,  Hee-Chul Yang ,  Hee-Chul Eun ,  In-Tae Kim ,  Han-Soo Lee ,  Hwan-Seo Park

IPC分类号： G21F9/14

CPC分类号： C25C3/34 ,  G21F9/06

摘要： A reuse apparatus of eutectic salt waste produced in an electro refining process and a method thereof is a technology that in order to collect the eutectic salt of the eutectic salt waste, oxidizes/precipitates nuclides (rare earth and TRU) within the eutectic salt waste, an oxygen dispersing method is used to perform a layer separation into the eutectic salt layer and the precipitate layer. Then, the precipitate layer and eutectic salt layer are separated and collected, so that the eutectic salt layer is directly reused and the eutectic salt within the precipitates is reused by separating and collecting it using distillation/condensation processes. The reuse apparatus of the eutectic salt waste and a method thereof thereby increases the collecting efficiency of the eutectic salt and allows the compositions of the collected eutectic salt to have the same compositions as the eutectic salt used in the electro refining process.

摘要翻译： 在电精炼工艺中生产的共晶盐水废弃物的再利用装置及其方法是为了收集共晶盐废物的共晶盐，在共晶盐废物内氧化/沉淀出核素（稀土和TRU） 使用氧分散法进行到共晶盐层和沉淀层的层分离。 然后，分离收集沉淀层和共晶盐层，使共晶盐层直接再利用，沉淀中的共晶盐通过使用蒸馏/缩合方法分离和收集而再利用。 共晶盐矿废弃物的再利用装置及其方法因此提高了共晶盐的收集效率，并且允许收集的共晶盐的组成与用于电精炼过程的共晶盐具有相同的组成。

公开(公告)号：US20100071408A1

公开(公告)日：2010-03-25

申请号：US12500869

申请日：2009-07-10

申请人： Yung-Zun Cho ,  In-Tae Kim ,  Han-Soo Lee

发明人： Yung-Zun Cho ,  In-Tae Kim ,  Han-Soo Lee

IPC分类号： B01D9/04 ,  C02F1/22 ,  F25D23/00

CPC分类号： B01D9/0013 ,  B01D9/005

摘要： Disclosed herein are a method of recycling LiCl salt wastes comprising radionuclides and an apparatus using the same. The method includes a) solidifying a LiCl salt contained in the LiCl salt wastes and contacting the outer wall of a housing, by charging a crystallizer comprising the housing having an internal accommodating space and an air cooler in the internal accommodating space into a crystallizing furnace accommodating the LiCl salt wastes comprising the radionuclides, and by cooling the housing to a temperature of two-phase region where the liquid state and the solid state of the LiCl salt waste coexist, b) separating the crystallizer where the LiCl salt is solidified from the crystallizing furnace, c) recycling the LiCl salt by heating the separated crystallizer to melt the solidified LiCl salt.

摘要翻译： 本文公开了一种回收包含放射性核素的LiCl盐废物的方法和使用其的装置。 该方法包括：将包含在LiCl盐废物中的LiCl盐固化并与壳体的外壁接触，通过将包含具有内部容纳空间的壳体和在内部容纳空间中的空气冷却器的结晶器装入容纳的结晶炉中 包括放射性核素的LiCl盐废物，并且通过将壳体冷却至液体状态和LiCl盐废物的固体状态共存的两相区域的温度，b）将LiCl盐固化的结晶器从结晶 炉，c）通过加热分离的结晶器来熔化固化的LiCl盐来回收LiCl盐。