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1. 发明专利

JP2002071882A MELTING METHOD OF SPENT FUEL ROD, AND APPARATUS THEREOF 失效
公开(公告)号：JP2002071882A
公开(公告)日：2002-03-12
申请号：JP2000265004
申请日：2000-09-01
申请人： TOSHIBA CORP , TOSHIBA ENGINEERING CO
发明人： MIKURA MICHITAKA , KANEKO MASAAKI , MURATA EIICHI , MATSUBAYASHI YOSHIKAZU , NAKAJIMA ATSUSHI
IPC分类号： G21C19/34 , B01F1/00 , G21C19/46
摘要： PROBLEM TO BE SOLVED: To melt a cladding tube of a spent fuel rod into an oxide suitable for a disposal environment, and to improve the electrolytic speed. SOLUTION: A lower portion of the spent fuel rod 12 is immersed in an electrolyte 7 consisting of nitric acid solution in an electrolytic tank 6. A cathode 8 is immersed in the electrolyte 7 with the spent fuel rod 12 as an anode, and the voltage is applied between the anode and the cathode 8. The cladding tube is separated and uranium fuel pellets are melted at the same time by the electrolytic oxidation of the spent fuel rod 12.

2. 发明专利

JP2002131482A MATERIAL AND METHOD FOR FIXING RADIOACTIVCHLORINE 失效
公开(公告)号：JP2002131482A
公开(公告)日：2002-05-09
申请号：JP2000324447
申请日：2000-10-24
申请人： TOSHIBA CORP , TOSHIBA ENGINEERING CO
发明人： MIKURA MICHITAKA , MURATA EIICHI , KANEKO MASAAKI , TAKAHASHI RIYOUTA , NAKAJIMA ATSUSHI
IPC分类号： G21F9/30 , B09B3/00 , C04B7/32 , C04B18/04 , C04B22/12 , C04B28/06 , C04B28/08 , G21F9/16
摘要： PROBLEM TO BE SOLVED: To provide a material and a method for fixing radioactivchlorine which adsorb a lot of it and can fix chlorine stably. SOLUTION: This solidifying material of radioactivchlorine includes alumina cement of 15 to 17 wt.% and the remaining is made of a calcium compound. The alumina cement is made of at least one selected from the first, second, third, fourth and fifth categories in the Japan Industrial Standards(JIS). The calcium compound is composed of at least one selected from calcium hydroxide, (Ca(OH)2), calcium oxide(CaO), calcium carbonate(CaCO3), calcium sulfate(CaSo4), calcium sulfite(CaSO3) and calcium nitrate(Ca(No3)2).

3. 发明专利

JP2009068947A Method and device for granulating radioactive waste 有权
标题翻译：用于生产放射性废物的方法和装置
公开(公告)号：JP2009068947A
公开(公告)日：2009-04-02
申请号：JP2007236613
申请日：2007-09-12
申请人： Toshiba Aitekku Kk , Toshiba Corp , 東芝アイテック株式会社 , 株式会社東芝
发明人： SATO TATSUAKI , MIKURA MICHITAKA , HARUGUCHI YOSHIKO , MURATA EIICHI , YAMASHITA TAKEO , SHOJI YUICHI , OKANO TOSHIAKI , KAWABE AKIHIRO , YASUMURA KEIJIRO
IPC分类号： G21F9/30
摘要： PROBLEM TO BE SOLVED: To provide a method and a device for granulating radioactive waste which make it possible to stably atomize a binder for granulating fine particles of the radioactive waste over a long period.
SOLUTION: The device is composed of a mixer tank 8 to which powdery radioactive waste is fed, a granulator 11 for granulating the radioactive waste mixed with the binder in the mixer tank 8, a nozzle 4 mounted on the mixer tank 8 to atomize the liquid binder over the powdery radioactive waste and an excitation means 5 to impart impulsive vibration to the nozzle 4.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：提供一种使放射性废物造粒的方法和装置，其可以稳定地雾化用于使放射性废物细颗粒成粒的长时间的粘合剂。解决方案：该装置由供给粉状放射性废物的混合罐8，混合罐8中与粘合剂混合的放射性废料造粒的造粒机11，安装在混合罐8上的喷嘴4 将粉末状放射性废物上的液体粘合剂雾化，以及激发装置5，以向喷嘴4施加脉冲振动。版权所有（C）2009，JPO＆INPIT

4. 发明专利

JP2004286627A Processing method and system of activated graphite 审中-公开
公开(公告)号：JP2004286627A
公开(公告)日：2004-10-14
申请号：JP2003079822
申请日：2003-03-24
申请人： Toshiba Corp , Toshiba Plant Systems & Services Corp , 東芝プラントシステム株式会社 , 株式会社東芝
发明人： TAKAHASHI RIYOUTA , HARUGUCHI YOSHIKO , MURATA EIICHI , MIKURA MICHITAKA , SATO KOKICHI , NAKAJIMA ATSUSHI
IPC分类号： G21F9/30
摘要： PROBLEM TO BE SOLVED: To provide a processing method and system of activated graphite which suppresses low the leaching of radioactive nuclide after embedding by lowering process of radioactive nuclide contained in the activated graphite.
SOLUTION: A heating furnace 1 for mixing and heating activated graphite 11 containing radioactive nuclide and high polymeric compound, inert gas supplying systems 3 and 4 for supplying inert gas in the heating furnace, an chloride trap 6 connected with the heating furnace and collecting chlorine gas and chlorine compound, and an alkali trap 8 connected with the chloride trap 6 and collecting carbon dioxide are provided.
COPYRIGHT: (C)2005,JPO&NCIPI

5. 发明专利

JP2004233156A Method and device for disposing waste liquid 有权
公开(公告)号：JP2004233156A
公开(公告)日：2004-08-19
申请号：JP2003020707
申请日：2003-01-29
申请人： Toshiba Corp , 株式会社東芝
发明人： TODA MASAMI , MURATA EIICHI , HARUGUCHI YOSHIKO , HOSAKA KATSUMI , SATO KOKICHI
IPC分类号： G21F9/06 , C02F1/32 , C02F1/42 , C02F1/70 , C02F9/00 , G21F9/12
摘要： PROBLEM TO BE SOLVED: To provide a method and device for disposing waste liquid, generating small amount of secondary wastes and also providing satisfactory work environment. SOLUTION: In a method for disposing waste liquid 1 including hexavalent chromium, formic acid 4 as is added to the waste liquid 1 a pH adjuster, hydrogen peroxide 5 is added thereto as a reducer to reduce the hexavalent chromium to trivalent chromium, and the formic acid is decomposed into carbon dioxide gas and water. COPYRIGHT: (C)2004,JPO&NCIPI

6. 发明专利

JP2003294888A Method and apparatus for processing radioactive waste, and its solidifying method 审中-公开
标题翻译：用于处理放射性废物的方法和装置及其固化方法
公开(公告)号：JP2003294888A
公开(公告)日：2003-10-15
申请号：JP2002094111
申请日：2002-03-29
申请人： Toshiba Corp , 株式会社東芝
发明人： HODOZUKA MASATOSHI , TOYOHARA NAOMI , MIKURA MICHITAKA , MURATA EIICHI , KANEKO MASAAKI , TAKAHASHI RIYOUTA , SAKAI HIROHIKO
IPC分类号： G21F9/06 , G21F9/02 , G21F9/10 , G21F9/16
摘要： PROBLEM TO BE SOLVED: To reuse salt waste produced by a dry-type reprocessing method, or to solidify it. SOLUTION: When spent fuel is reprocessed by the dry method, waste of fused salt being an chloride of alkaline metal is produced. After this waste 1 of spent fused salt is dissolved 2 in water, this aqueous solution is electrolytically dialyzed 3. Consequently, impurities are removed, and fused salt being a chloride of alkaline metal is recovered as an aqueous solution of a hydroxide of the alkaline metal. The recovered aqueous solution is caused to react with hydrochloric acid, and is reused again as fused salt. The recovered processed solution 4 is solidified and reused 5. Namely, it is solidified into waste, or it is reacted with phosphoric acid to produce phosphate, and the phosphate is vitrified. COPYRIGHT: (C)2004,JPO
摘要翻译：要解决的问题：重新使用由干式再加工方法生产的盐类废物或使其固化。
解决方案：当废燃料通过干法再处理时，产生作为碱金属氯化物的熔融盐的浪费。废弃的1熔融盐溶解后，将该水溶液2溶解在水中，将该水溶液进行电解透析3.因此，除去杂质，作为碱金属的氢氧化物的水溶液回收作为碱金属的氯化物的熔融盐。使回收的水溶液与盐酸反应，并再次作为熔融盐再次使用。回收的处理溶液4固化并重新使用5.即，其被固化成废物，或者与磷酸反应以产生磷酸盐，并且磷酸盐被玻璃化。版权所有（C）2004，JPO

7. 发明专利

JP2003014890A Disposal method for radioactivated graphite and its system 审中-公开
标题翻译：放射性石墨及其系统的处理方法
公开(公告)号：JP2003014890A
公开(公告)日：2003-01-15
申请号：JP2001196395
申请日：2001-06-28
申请人： Toshiba Corp , 株式会社東芝
发明人： TAKAHASHI RIYOUTA , MIKURA MICHITAKA , MURATA EIICHI , TOYOHARA NAOMI , SATO TATSUAKI , NATSUI KAZUJI
IPC分类号： G21F9/28 , B08B3/12 , B09B3/00 , G21F9/06 , G21F9/32
摘要： PROBLEM TO BE SOLVED: To remove radioactive nucleides adhering to activated graphite and reduce discharge of radioactive nucleides from the activated graphite to be buried.
SOLUTION: The activated graphite is washed with ultrasonic or a chemical decontamination agent and C-14 in washing liquid is mineralized and C1-36 is recovered by adsorption. By heating the activated graphite after washing, included C1-36 is removed by evaporation. The heated activated graphite is solidified. For the condition of washing activated graphite, it is proper to irradiate with ultrasonic in solution of oxidation processing below pH 4 and temperature of nearly 80°C. The heating processing of the activated graphite is proper to heat from below to 900°C under the existence of inert gas. C1-36 is recovered in a trap which a cooling device is installed.
COPYRIGHT: (C)2003,JPO
摘要翻译：要解决的问题：去除附着在活性石墨上的放射性核，并减少活性石墨放射性核素的放电。解决方案：活性石墨用超声波或化学去污剂洗涤，洗涤液中的C-14矿化，通过吸附回收C1-36。洗涤后加热活性石墨，通过蒸发除去C36。加热的活化石墨被固化。对于活性石墨的清洗条件，适当的是超声波照射超过pH4的氧化处理和接近80摄氏度的温度。在惰性气体的存在下，活性石墨的加热处理适宜于从低到900℃。在安装冷却装置的陷阱中回收C1-36。

8. 发明专利

JP2017082264A ガラス固化体の溶解方法及びその溶解装置审中-公开
公开(公告)号：JP2017082264A
公开(公告)日：2017-05-18
申请号：JP2015209849
申请日：2015-10-26
申请人：株式会社東芝 , Toshiba Corp
发明人： KANEMURA SHOHEI , TAKAHASHI YUYA , KANEKO MASAAKI , YAMASHITA TAKEO , MURATA EIICHI , OMORI TAKASHI , NOHIRA TOSHIYUKI , YASUDA KOJI , KATASHO YUMI
IPC分类号： C25B1/00 , B09B3/00 , B09B5/00 , G21F9/30
摘要：【課題】簡易にガラス固化体を溶解できるとともに、溶解処理に伴う2次廃棄物量を低減できるガラス固化体の溶解技術を提供する。【解決手段】ガラス固化体の溶解方法は、ガラス固化体11を保持槽の内部に保持された溶融塩13に浸漬させる溶融塩浸漬工程S10と、ガラス固化体11に陰極を接触させて電解還元する電解還元工程S11と、を含む。【選択図】図4

9. 发明专利

JP2010190749A Nuclide separation processing method and system 审中-公开
标题翻译： NUCLIDE分离处理方法和系统
公开(公告)号：JP2010190749A
公开(公告)日：2010-09-02
申请号：JP2009035842
申请日：2009-02-18
申请人： Toshiba Corp , 株式会社東芝
发明人： KANEKO MASAAKI , HARUGUCHI YOSHIKO , MURATA EIICHI , YAMASHITA TAKEO , MIKURA MICHITAKA , OBATA MASAMICHI , HORIMOTO TAICHI
IPC分类号： G21F9/10 , G21F9/06
摘要： PROBLEM TO BE SOLVED: To provide a nuclide separation processing method and a system allowing easy operation and for further improving removal of nuclides.
SOLUTION: An iron cosedimentation of Co, Ni, etc. is produced by introducing an iron ion into a waste liquid treated with high-temperature and high-pressure water of an ion exchange resin used for a reactor water cleanup system and controlling pH, and a magnetic powder is introduced in order to add a coprecipitating ability to the cosedimentation. Then a supernatant and the cosedimentation are subjected to solid-liquid separation.
COPYRIGHT: (C)2010,JPO&INPIT

10. 发明专利

JP2006317290A Nuclide separation method of radioactive waste, nuclide sample production method, and uranium analysis method 审中-公开
标题翻译：放射性废物的核素分离方法，核素样品生产方法和铀分析方法
公开(公告)号：JP2006317290A
公开(公告)日：2006-11-24
申请号：JP2005140364
申请日：2005-05-12
申请人： Toshiba Corp , 株式会社東芝
发明人： MURATA EIICHI , HARUGUCHI YOSHIKO , MIKURA MICHITAKA , SATO KOKICHI
IPC分类号： G01N1/10 , G01T1/167 , G01T7/02
摘要： PROBLEM TO BE SOLVED: To provide a new separation method of a nuclide included in radioactive waste, and a method for simple uranium quantitative analysis in the radioactive waste.
SOLUTION: In step S1, hydrofluoric acid aqueous solution wherein the nuclide in the radioactive waste is dissolved is prepared and produced. In step S2, ion-exchange adsorption of the nuclide dissolved in the hydrofluoric acid aqueous solution is performed by using a fluorine-ion type anion-exchange resin. In step S3, the nuclide subjected to the ion-exchange adsorption onto the anion-exchange resin is selectively eluted and separated by a prescribed chemical medical solution. In step S4, the nuclide is subjected to coprecipitation separation by adding, for example, samarium. In step S5, measurement of an α-ray spectrum of a coprecipitate is performed. Thus, for example, identification of an uranium isotope in the radioactive waste and its quantitative analysis can be performed simply.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供放射性废物中包含的核素的新分离方法，以及放射性废物中简单铀定量分析的方法。解决方案：在步骤S1中，制备并生产放射性废物中的核素溶解的氢氟酸水溶液。在步骤S2中，使用氟离子型阴离子交换树脂进行溶解在氢氟酸水溶液中的核素的离子交换吸附。在步骤S3中，经阴离子交换树脂进行离子交换吸附的核素被规定的化学药液选择性地洗脱分离。在步骤S4中，通过添加例如钐将核素进行共沉淀分离。在步骤S5中，进行共沉淀物的α射线谱的测定。因此，例如，可以简单地进行放射性废物中的铀同位素的鉴定及其定量分析。版权所有（C）2007，JPO＆INPIT

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