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公开(公告)号：US20130296629A1
公开(公告)日：2013-11-07
申请号：US13871037
申请日：2013-04-26
发明人： Suk Ju Cho , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim , Wook Jin Han , Jae Bong Ryu , Hyun Gyu Kang
IPC分类号： G21F9/30
CPC分类号： G21F9/308 , G21F9/30 , G21F9/301 , G21F9/34 , Y10S588/901
摘要： Disclosed herein is a method of treating radioactive metal waste using melt decontamination, wherein radioactive metal waste, which is generated from nuclear fuel processing facilities or nuclear fuel production facilities, and which cannot be easily treated by surface decontamination because it has a complicated geometric shape, and the surface contamination of which cannot be measured, can be treated by melt decontamination. The method is advantageous in that radioactive metal waste, which cannot be treated by conventional surface decontamination, can be treated, so that radioactive metal waste can be recycled, thereby obtaining economic profits, and further in that a large storage space necessary for cutting and then storing radioactive metal waste is not required, and in that excessive manpower and cost are not required.
摘要翻译： 本文公开了一种使用熔融去污处理放射性金属废物的方法，其中由核燃料处理设施或核燃料生产设备产生的放射性金属废物，由于其具有复杂的几何形状而不能容易地通过表面去污处理， 并且其表面污染物无法测量，可以通过熔体去污处理。 该方法的优点在于，可以处理不能通过常规表面去污处理的放射性金属废物，从而可以回收放射性金属废物，从而获得经济利益，进一步地，切割所需的大量储存空间 不需要储存放射性金属废物，因此不需要过多的人力和费用。
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公开(公告)号：US09253825B2
公开(公告)日：2016-02-02
申请号：US13871051
申请日：2013-04-26
发明人： Suk Ju Cho , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim , Wook Jin Han , Jae Bong Ryu , Hyun Gyu Kang
摘要： A melting apparatus for melt-decontaminating radioactive metal waste includes a melting furnace, a high frequency generator, a ladle, a bogie, a cooling unit and a dust collector. In detail, the melting furnace includes a crucible into which the metal waste is input, and an induction coil which is wound around the crucible to melt the metal waste. The induction coil has a hollow hole in which cooling fluid flows. The high frequency generator applies high-frequency current to the induction coil. The ladle supplies molten metal, from which slag has been removed in the crucible, into molds. The bogie is disposed adjacent to the ladle and is provided with the molds, each of which forms an ingot using the molten metal supplied thereinto. The cooling unit cools the cooling fluid and circulates it along the induction coil. The dust collector filters out dust and purifies gas.
摘要翻译： 用于熔融净化放射性金属废料的熔化装置包括熔炉，高频发生器，钢包，转向架，冷却单元和集尘器。 详细地说，熔炉包括输入金属废料的坩埚和卷绕在坩埚上的熔化金属废料的感应线圈。 感应线圈具有冷却流体流动的中空孔。 高频发生器对感应线圈施加高频电流。 钢包将熔融金属从坩埚中取出，进入模具。 转向架设置在钢包附近，并设置有模具，每个模具使用供应的熔融金属形成锭。 冷却单元冷却冷却流体并沿着感应线圈使其循环。 除尘器除尘，净化气体。
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公开(公告)号：US20130294473A1
公开(公告)日：2013-11-07
申请号：US13871051
申请日：2013-04-26
发明人： Suk Ju CHO , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim , Wook Jin Han , Jae Bong Ryu , Hyun Gyu Kang
摘要： Disclosed herein is a melting apparatus for melt-decontaminating radioactive metal waste. The melting apparatus includes a melting furnace, a high frequency generator, a ladle, a bogie, a cooling unit and a dust collector. The melting furnace includes a crucible into which the metal waste is input, and an induction coil which is wound around the crucible to melt the metal waste. The induction coil has a hollow hole in which cooling fluid flows. The high frequency generator applies high-frequency current to the induction coil. The ladle supplies molten metal, from which slag has been removed in the crucible, into molds. The bogie is disposed adjacent to the ladle and is provided with the molds, each of which forms an ingot using the molten metal supplied thereinto. The cooling unit cools the cooling fluid and circulates it along the induction coil. The dust collector filters out dust and purifies gas.
摘要翻译： 本文公开了一种用于对放射性金属废物进行熔融净化的熔化装置。 熔化装置包括熔炉，高频发生器，钢包，转向架，冷却单元和集尘器。 熔炉包括输入金属废料的坩埚和缠绕在坩埚上的熔化金属废料的感应线圈。 感应线圈具有冷却流体流动的中空孔。 高频发生器对感应线圈施加高频电流。 钢包将熔融金属从坩埚中取出，进入模具。 转向架设置在钢包附近，并设置有模具，每个模具使用供应的熔融金属形成锭。 冷却单元冷却冷却流体并沿着感应线圈使其循环。 除尘器除尘，净化气体。
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公开(公告)号：US09880290B2
公开(公告)日：2018-01-30
申请号：US13873340
申请日：2013-04-30
发明人： Suk Ju Cho , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim , Jae Bong Ryu
CPC分类号： G01T1/167
摘要： Disclosed is a method of measuring radioactive material of an ingot, in which an ingot having a volume produced by subjecting metal waste generated in nuclear fuel processing or production facilities to melting decontamination undergoes gamma spectroscopy using a HPGe detector to measure gamma rays of U-235 (185.72 keV, 57.2%) among uranium isotopes, followed by performing detector calibration using a certified reference material and self-absorption correction depending on the density of a medium using MCNP computer code, and which enables rapid determination of whether the ingot subjected to melting decontamination may be self-disposed of or not.
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公开(公告)号：US08829261B2
公开(公告)日：2014-09-09
申请号：US13871037
申请日：2013-04-26
发明人： Suk Ju Cho , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim , Wook Jin Han , Jae Bong Ryu , Hyun Gyu Kang
CPC分类号： G21F9/308 , G21F9/30 , G21F9/301 , G21F9/34 , Y10S588/901
摘要： Disclosed herein is a method of treating radioactive metal waste using melt decontamination, wherein radioactive metal waste, which is generated from nuclear fuel processing facilities or nuclear fuel production facilities, and which cannot be easily treated by surface decontamination because it has a complicated geometric shape, and the surface contamination of which cannot be measured, can be treated by melt decontamination. The method is advantageous in that radioactive metal waste, which cannot be treated by conventional surface decontamination, can be treated, so that radioactive metal waste can be recycled, thereby obtaining economic profits, and further in that a large storage space necessary for cutting and then storing radioactive metal waste is not required, and in that excessive manpower and cost are not required.
摘要翻译： 本文公开了一种使用熔融去污处理放射性金属废物的方法，其中由核燃料处理设施或核燃料生产设备产生的放射性金属废物，由于其具有复杂的几何形状而不能容易地通过表面去污处理， 并且其表面污染物无法测量，可以通过熔体去污处理。 该方法的优点在于，可以处理不能通过常规表面去污处理的放射性金属废物，从而可以回收放射性金属废物，从而获得经济利益，进一步地，切割所需的大量储存空间 不需要储存放射性金属废物，因此不需要过多的人力和费用。
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6.发明授权公开(公告)号：US08796500B2
公开(公告)日：2014-08-05
申请号：US13870745
申请日：2013-04-25
发明人： Suk Ju Cho , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim
IPC分类号： A62D1/00
摘要： Disclosed is a method of disposing of radioactive metal waste using melting decontamination, including sorting radioactive metal waste generated in nuclear fuel processing or production facilities by predetermined sorting criteria, and charging sorted metal waste into a melting furnace so as to be melted; adding a impurity remover to the melt of the melting furnace to remove generated slag; pouring the melt having no slag into a mold to form an ingot; subjecting the ingot to gamma spectroscopy using a gamma spectrometer to measure gamma rays of U-235 (185.72 keV, 57.2%) among uranium isotopes, performing detector calibration using a certified reference material and self-absorption correction depending on the density of a medium using MCNP computer code, and calculating total radioactivity of the ingot from the quantified radioactivity and mass of U-235; and efficiently and rapidly determining whether the ingot subjected to radioactivity measurement satisfies a clearance limit.
摘要翻译： 公开了一种使用熔融去污处理放射性金属废物的方法，包括通过预定的分选标准分选在核燃料加工或生产设备中产生的放射性金属废物，并将分选的金属废料装入熔化炉中以熔化; 向熔化炉的熔体中加入杂质去除剂以除去产生的炉渣; 将没有渣的熔体倒入模具中以形成锭; 使用伽马光谱仪对晶锭进行伽马光谱测量，以测量铀同位素中的铀-235（185.72keV，57.2％）的伽马射线，使用认证参考材料进行检测器校准，并根据使用的介质的密度进行自吸收校正 MCNP计算机代码，并从U-235的量化放射性和质量计算锭的总放射性; 并且有效且快速地确定经受放射性测量的锭是否满足间隙极限。
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7.发明申请公开(公告)号：US20130296628A1
公开(公告)日：2013-11-07
申请号：US13870745
申请日：2013-04-25
发明人： Suk Ju CHO , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim
摘要： Disclosed is a method of disposing of radioactive metal waste using melting decontamination, including sorting radioactive metal waste generated in nuclear fuel processing or production facilities by predetermined sorting criteria, and charging sorted metal waste into a melting furnace so as to be melted; adding a impurity remover to the melt of the melting furnace to remove generated slag; pouring the melt having no slag into a mold to form an ingot; subjecting the ingot to gamma spectroscopy using a gamma spectrometer to measure gamma rays of U-235 (185.72 keV, 57.2%) among uranium isotopes, performing detector calibration using a certified reference material and self-absorption correction depending on the density of a medium using MCNP computer code, and calculating total radioactivity of the ingot from the quantified radioactivity and mass of U-235; and efficiently and rapidly determining whether the ingot subjected to radioactivity measurement satisfies a clearance limit.
摘要翻译： 公开了一种使用熔融去污处理放射性金属废物的方法，包括通过预定的分选标准分选在核燃料加工或生产设备中产生的放射性金属废物，并将分选的金属废料装入熔化炉中以熔化; 向熔化炉的熔体中加入杂质去除剂以除去产生的炉渣; 将没有渣的熔体倒入模具中以形成锭; 使用伽马光谱仪对晶锭进行伽马光谱测量，以测量铀同位素中的铀-235（185.72keV，57.2％）的γ射线，使用认证参考材料进行检测器校准，并根据使用的介质的密度进行自吸收校正 MCNP计算机代码，并从U-235的量化放射性和质量计算锭的总放射性; 并且有效且快速地确定经受放射性测量的锭是否满足间隙极限。
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公开(公告)号：US09880289B2
公开(公告)日：2018-01-30
申请号：US13873328
申请日：2013-04-30
发明人： Suk Ju Cho , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim , Jae Bong Ryu
CPC分类号： G01T1/167
摘要： Disclosed is a method of measuring radioactive material of an ingot, in which an ingot having a volume produced by subjecting metal waste generated in nuclear fuel processing or production facilities to melting decontamination undergoes gamma spectroscopy using a NaI detector to measure gamma rays of U-235 (185.72 keV, 57.2%) among uranium isotopes, followed by performing detector calibration using a certified reference material and self-absorption correction depending on the density of a medium using MCNP computer code, and which enables rapid determination of whether the ingot subjected to melting decontamination may be self-disposed of or not.
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9.发明申请METHOD OF MEASURING RADIOACTIVE MATERIAL OF INGOT USING HPGe GAMMA SCINTILLATOR 有权使用HPGe GAMMA SCINTILLATOR测量放射性物质的方法公开(公告)号：US20130297229A1
公开(公告)日：2013-11-07
申请号：US13873340
申请日：2013-04-30
发明人： Suk Ju CHO , Young Bae Lee , Jeung Gun Seol , Yong Jae Kim , Jae Bong Ryu
IPC分类号： G01T1/167
CPC分类号： G01T1/167
摘要： Disclosed is a method of measuring radioactive material of an ingot, in which an ingot having a volume produced by subjecting metal waste generated in nuclear fuel processing or production facilities to melting decontamination undergoes gamma spectroscopy using a HPGe detector to measure gamma rays of U-235 (185.72 key, 57.2%) among uranium isotopes, followed by performing detector calibration using a certified reference material and self-absorption correction depending on the density of a medium using MCNP computer code, and which enables rapid determination of whether the ingot subjected to melting decontamination may be self-disposed of or not.
摘要翻译： 公开了一种测量锭的放射性物质的方法，其中通过使在核燃料处理或生产设备中产生的金属废物经过熔融去污而产生的体积的锭通过使用HPGe检测器进行伽马光谱测量来测量U-235的γ射线 （185.72键，57.2％），然后使用认证参考材料进行检测器校准，并使用MCNP计算机代码根据介质的密度进行自吸收校正，并能快速确定晶锭是否熔化 去污可能是自行处理的。
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