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1. 发明专利

JP2013170921A Method and apparatus for re-storing radioactive waste 有权
标题翻译：重新储存放射性废物的方法和装置
公开(公告)号：JP2013170921A
公开(公告)日：2013-09-02
申请号：JP2012034757
申请日：2012-02-21
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： MIYAKE SHUNSUKE , TAMADA SHIN , IINO KENJI
IPC分类号： G21F9/30 , G21F9/22
摘要： PROBLEM TO BE SOLVED: To improve storage efficiency of radioactive waste containing used filter sludge.SOLUTION: A method for re-storing radioactive waste is characterized in extracting the radioactive waste containing at least cellulose fibers stored within a storage tank, decomposing at least a part of the cellulose fibers through hydrolytic decomposition and oxidative decomposition, transferring slurry containing a residue after the decomposition to the storage tank, and storing the slurry.
摘要翻译：要解决的问题：提高含有废弃过滤污泥的放射性废物的储存效率。解决方案：放射性废物再储存的方法的特征在于提取至少含有储存在储罐中的纤维素纤维的放射性废物，分解至少一部分的纤维素纤维通过水解分解和氧化分解，在分解后将含有残余物的浆料转移到储罐中，并储存浆料。

2. 发明专利

JP2010133984A Treating method of spent fuel, and fuel cycle system 有权
标题翻译：燃料燃料和燃料循环系统的处理方法
公开(公告)号：JP2010133984A
公开(公告)日：2010-06-17
申请号：JP2010061174
申请日：2010-03-17
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： YAMASHITA JUNICHI , SASAHIRA AKIRA , KAWAMURA FUMIO , FUKAZAWA TETSUO , HOSHINO KUNIYOSHI , IINO KENJI
IPC分类号： G21C19/44
CPC分类号： Y02W30/882
摘要： PROBLEM TO BE SOLVED: To provide a treating method of spent fuel and a cycle system, which simplify a reprocessing plant of thermal reactor spent fuel, compact the plant, and reduce the cost. SOLUTION: The spent fuel discharged from a nuclear power plant (thermal reactor power plant) is conveyed to a volume decreasing facility for reducing the volume and weight of the spent fuel by removing uranium. The volume of the spent fuel is reduced by removing a large part of uranium, the decreased spent fuel in volume is stored as needed, and is conveyed to the reprocessing plant of fast neutron reactor spent fuel, uranium and plutonium are extracted, and fast neutron reactor fuel is fabricated. COPYRIGHT: (C)2010,JPO&INPIT
摘要翻译：要解决的问题：为了提供乏燃料的处理方法和循环系统，其简化了热反应堆乏燃料的后处理装置，压实了工厂，并降低了成本。解决方案：从核电站（热电厂发电厂）排放的乏燃料被运送到减小排放设施，以通过去除铀来减少乏燃料的体积和重量。通过去除大部分铀来减少乏燃料的体积，根据需要储存体积减少的乏燃料，并被输送到快中子反应堆乏燃料的后处理厂，铀和钚被提取，快中子制造反应堆燃料。版权所有（C）2010，JPO＆INPIT

3. 发明专利

JP2012032250A Sodium condensing removal device for fast breeder reactor cover gas system 审中-公开
标题翻译：用于快速BREEDER反应器盖气体系统的SODIUM CONDENSING REMOVAL DEVICE
公开(公告)号：JP2012032250A
公开(公告)日：2012-02-16
申请号：JP2010171311
申请日：2010-07-30
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： IINO KENJI
IPC分类号： G21C19/30 , G21D1/02
CPC分类号： Y02E30/40
摘要： PROBLEM TO BE SOLVED: To improve the sodium collection efficiency of a sodium condensing removal device.SOLUTION: The sodium condensing removal device includes: a vessel containing a filler for removing sodium; an inlet pipe which is attached to the vessel above the filler and supplies a gas containing sodium; an outlet pipe which is attached to the vessel below the filler and discharges a gas from which the sodium has been removed; and a heater which heats the inlet pipe. The device provides an improved sodium collection efficiency.
摘要翻译：要解决的问题：提高钠冷凝去除装置的钠收集效率。解决方案：钠冷凝去除装置包括：容纳用于除去钠的填料的容器; 入口管，其连接到填料上方的容器并供应含钠的气体; 出口管，其连接到填充物下方的容器并排出已从其中除去钠的气体; 以及加热入口管的加热器。该装置提供了提高的钠收集效率。版权所有（C）2012，JPO＆INPIT

4. 发明专利

JP2014020962A Radioactive wastewater treatment method and treatment device for the same 审中-公开
标题翻译：放射性废水处理方法及其处理装置
公开(公告)号：JP2014020962A
公开(公告)日：2014-02-03
申请号：JP2012160691
申请日：2012-07-19
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： IINO KENJI , TAMADA SHIN , MIYAKE SHUNSUKE
IPC分类号： G21F9/06
摘要： PROBLEM TO BE SOLVED: To provide a radioactive wastewater treatment method and a treatment device for the same capable of reducing generation of concentrated water to be treated by increasing a concentration thereof and continuously treating the wastewater.SOLUTION: Wastewater containing radioactive substances is supplied to a wastewater reception tank 2. The wastewater in the wastewater reception tank 2 is then: supplied to a reverse osmosis membrane treatment device 5 by a wastewater supply pump 4 through a wastewater supply pipe passage 3 connected to the wastewater reception tank 2; and separated into permeated water and concentrated water by the reverse osmosis membrane treatment device 5. A portion of the concentrated water separated by the reverse osmosis membrane treatment device 5 is discharged through a concentrated water transfer pipe passage 7 connected to a concentrated water discharging side of the reverse osmosis membrane treatment device 5. The remaining concentrated water separated by the reverse osmosis membrane treatment device 5 is circulated to an upstream side thereof through a circulation pipe passage 8 branched from the concentrated water transfer pipe passage 7.
摘要翻译：要解决的问题：提供一种放射性废水处理方法及其处理装置，其能够通过增加其浓度和连续处理废水来减少待处理的浓缩水的产生。解决方案：将含有放射性物质的废水供应到废水接收罐2.然后，废水接收罐2中的废水通过废水供给泵4通过与废水接收罐2连接的废水供给管路3供给反渗透膜处理装置5; 并通过反渗透膜处理装置5分离成透过水和浓缩水。由反渗透膜处理装置5分离的一部分浓缩水通过浓缩水输送管路7排出，浓缩水输送管路7与浓缩水排出侧反渗透膜处理装置5.由反渗透膜处理装置5分离的剩余浓缩水通过从浓缩水输送管道7分支的循环管路8循环到其上游侧。

5. 发明专利

JP2008151672A Spent nuclear fuel reprocessing method 有权
标题翻译：节能核燃料代用方法
公开(公告)号：JP2008151672A
公开(公告)日：2008-07-03
申请号：JP2006340649
申请日：2006-12-19
申请人： Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
发明人： IINO KENJI , HOSHINO KUNIYOSHI , KAWAMURA FUMIO , SASAHIRA AKIRA , HINO YUKO
IPC分类号： G21C19/44
CPC分类号： Y02W30/882
摘要： PROBLEM TO BE SOLVED: To secure stable operation of a reprocessing facility for a spent nuclear fuel. SOLUTION: Plutonium fluoride in fluorides evaporated by applying fluorine to the spent nuclear fuel by a fluorination device 2 is immobilized by an immobilization agent 10 in a Pu immobilization device 4, and the immobilized plutonium fluoride is reacted with steam in an oxide conversion device 7 together with the immobilization agent to acquire a raw material for a mixed oxide fuel, and a non-immobilized portion is reproduced as uranium hexafluoride by a U refining device 6. The immobilization agent adopted in an immobilization process is prepared by dehumidifying the inside of the Pu immobilization device 4 filled with a parent metal UO 2 for the immobilization agent inside by a vacuum pump 5, and by circulating, in the dehumidified inside, fluorine which is a reaction fluid for preparing the parent metal into the immobilization agent through a flow rate controller 3 into the inside thereof in a dehumidified dry environment. COPYRIGHT: (C)2008,JPO&INPIT
摘要翻译：要解决的问题：确保废核燃料的后处理设施的稳定运行。解决方案：通过氟化装置2通过将氟施加到废核燃料上蒸发的氟化钚中的氟化钚通过固定化剂10固定在Pu固定装置4中，并且将固定的钚氟化物与氧气转化反应装置7与固定剂一起获得用于混合氧化物燃料的原料，非固定部分通过U精制装置6再现为六氟化铀。固定方法中采用的固定剂是通过对内部进行除湿的用于固定剂的母体金属UO 2 的Pu固定装置4由真空泵5内部循环，并且在除湿的内部循环氟作为制备母体的反应流体金属在除湿干燥环境中通过流量控制器3进入其内部。版权所有（C）2008，JPO＆INPIT

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