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51. 发明专利

JP2008286525A Method and device for solidifying radioactive waste 有权
标题翻译：用于固化放射性废物的方法和装置
公开(公告)号：JP2008286525A
公开(公告)日：2008-11-27
申请号：JP2007128895
申请日：2007-05-15
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMASHITA TAKEO , KANEKO MASAAKI , HARUGUCHI YOSHIKO , MIKURA MICHITAKA , SATO TATSUAKI , KOMATSUBARA MASARU
IPC分类号： G21F9/30 , G21F9/16
摘要： PROBLEM TO BE SOLVED: To provide a method for solidifying radioactive waste and a device therefor which can inhibit inclination of a gas in a container to become flammable due to rise of the pressure in the container or generated hydrogen.
SOLUTION: The method for solidifying radioactive waste comprises a mixture accommodating step wherein a mixture of radioactive waste containing radionuclide(s) and solidifying material is accommodated in a solidifying container, and a water stability improver adding step wherein a water stability improver is added to the mixture before the mixture is accommodated in the solidifying container, or wherein the water stability improver is added to the solidifying container before or after the mixture is accommodated in the solidifying container. The water stability improver maintains an electric potential at which water can be stable under alkaline conditions in a solidified body obtained by solidifying the mixture.
COPYRIGHT: (C)2009,JPO&INPIT
摘要翻译：要解决的问题：提供一种固化放射性废物的方法及其装置，其可以抑制容器中的气体由于容器或产生的氢气中的压力升高而变得易燃的倾向。解决方案：固化放射性废物的方法包括混合物容纳步骤，其中将含有放射性核素的放射性废物和固化材料的混合物容纳在固化容器中，以及水稳定性改进剂添加步骤，其中水稳定性改进剂为在将混合物容纳在固化容器中之前加入到混合物中，或者在将混合物容纳在凝固容器中之前或之后将水稳定性改进剂加入固化容器中。水稳定性改进剂在通过固化混合物获得的凝固体中保持水在碱性条件下稳定的电位。版权所有（C）2009，JPO＆INPIT

52. 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

53. 发明专利

JP2006256872A Microchip, apparatus and method for producing hydrogen-producing raw material 审中-公开
标题翻译：微生物，生产氢原料的装置和方法
公开(公告)号：JP2006256872A
公开(公告)日：2006-09-28
申请号：JP2005072160
申请日：2005-03-15
申请人： Toshiba Corp , 株式会社東芝
发明人： MIZUGUCHI KOJI , TAKAHASHI RIYOUTA , MURAKAMI KAZUO , TAKASE HARUHIKO , NAKAMURA HIDEKI , MIKURA MICHITAKA , UTSUNOMIYA KAZUHIRO
IPC分类号： C01B3/02 , B01J19/00 , C01B3/04 , C01B7/14
CPC分类号： Y02E60/364
摘要： PROBLEM TO BE SOLVED: To reduce the amount of iodine used in hydrogen production through an IS (Iodine-Sulfur) method wherein water is decomposed by iodine and sulfur dioxide.
SOLUTION: A microchip for producing a hydrogen-producing raw material is equipped with a plurality of injection microchannels 1a, 1b and 1c through each of which different fluid is injected, a reaction microchannel 2 in which the fluids injected through the injection microchannels 1a, 1b and 1c are combined to produce the hydrogen-producing raw material through a chemical reaction and a plurality of separation microchannesl 3a, 3b and 3c for dividing liquid that comes out from the reaction microchannel 2. The reaction microchannel 2 has separating means 4 along the extensions of boundaries between the injection microchannels 1a, 1b and 1c. The separating means 4 assist separation of the flow inside the reaction microchannel 2 and also allow substantial mixing.
COPYRIGHT: (C)2006,JPO&NCIPI
摘要翻译：要解决的问题：通过碘（二氧化硫）分解水中的IS（碘 - 硫）法减少生产氢的碘量。解决方案：用于制造生产氢原料的微芯片配备有多个通过注入不同流体的注入微通道1a，1b和1c，反应微通道2，其中通过注射微通道注入的流体将1a，1b和1c组合起来，通过化学反应制造生产氢的原料，以及多个用于分离从反应微通道2出来的液体的分离微通道3a，3b和3c。反应微通道2具有分离装置4 沿着注射微通道1a，1b和1c之间的边界的延伸。分离装置4有助于分离反应微通道2内部的流并且还允许大量混合。版权所有（C）2006，JPO＆NCIPI

54. 发明专利

JP2015054282A 溶質の回収方法および溶質の回収装置审中-公开
标题翻译：解决方案和解决方案的恢复方法
公开(公告)号：JP2015054282A
公开(公告)日：2015-03-23
申请号：JP2013188848
申请日：2013-09-11
申请人：株式会社東芝 , Toshiba Corp
发明人： MIYAMOTO MASAYA , IKEI SHUKO , KAWAUCHI KANAE , NAGAMORI YASUHIKO , YAMASHITA TAKEO , MIKURA MICHITAKA
IPC分类号： C02F1/62 , C02F1/58
摘要：【課題】重金属およびリンを含有する強酸性の溶液から、重金属類とリンを選択的に回収することが可能な、溶質の回収方法および溶質の回収装置を提供することを目的とする。【解決手段】実施形態の溶質の回収方法は、初期溶液に重金属除去剤を添加する重金属除去ステップと、重金属除去剤が添加された初期溶液を第1の液相と第1の固相に固液分離する第1の固液分離ステップと、第1の液相にリン除去剤を添加するリン除去ステップと、リン除去剤が添加された第1の液相を第2の液相と第2の固相に固液分離する第2の固液分離ステップと、を備え、初期溶液は焼却灰から放射性核種を抽出した後に放射性核種が回収された溶液であるものとする。【選択図】図3
摘要翻译：要解决的问题：提供能够从包括重金属和磷的强酸性溶液中选择性地回收重金属和磷的溶质的溶质和回收装置的回收方法。解决方案：实施方案的溶质回收方法包括将重金属去除剂添加到初始溶液中的重金属去除步骤，将已经添加有重金属去除剂的初始溶液固液分离到第一液相中的第一固液分离步骤和第一固相，磷除去步骤，向第一液相中加入除磷剂;以及第二固 - 液分离步骤，将已经加入除磷剂的第一液相固液分离到第二液相中，第二固相; 初始溶液是通过从焚烧灰中提取放射性核素然后回收放射性核素获得的溶液。

55. 发明专利

JP2014173905A Radioactive cesium elution processing method and radioactive cesium elution processor 审中-公开
标题翻译：放射性电解质处理方法和放射性电解质处理器
公开(公告)号：JP2014173905A
公开(公告)日：2014-09-22
申请号：JP2013044794
申请日：2013-03-06
申请人： Toshiba Corp , 株式会社東芝
发明人： MIYAMOTO MASAYA , KAWAUCHI KANAE , SUGIMORI TOSHIAKI , ABE HIROKO , NAKAMURA HIDEKI , KANEKO MASAAKI , MIKURA MICHITAKA , MINE TETSUYA , TODOROKI TOMOHIRO
IPC分类号： G21F9/28 , G21F9/12
摘要： PROBLEM TO BE SOLVED: To provide a radioactive cesium elution processing method which allows efficient and effective elution of radioactive cesium from an object substance by reducing a precipitation amount of calcium oxalate resulting from a reaction between the object substance and an oxalic acid and a radioactive cesium elution processor.SOLUTION: The radioactive cesium elution processing method is a processing method of mixing an object substance containing calcium and radioactive cesium and an eluant containing oxalic acid which includes a mixing step S1 of mixing an elution accelerator which reduces a precipitation amount of calcium oxalate resulting from a reaction between the object substance and oxalic acid, an eluant containing oxalic acid and the object substance.
摘要翻译：要解决的问题：提供一种放射性铯洗脱处理方法，其通过减少由物体和草酸与放射性铯之间的反应产生的草酸钙的沉淀量，从而有效和有效地从目标物质洗脱放射性铯洗脱处理器。解决方案：放射性铯洗脱处理方法是将含有钙和放射性铯的目标物质和含有草酸的洗脱剂混合的处理方法，其包括混合步骤S1，其混合降低草酸钙沉淀量的洗脱促进剂由目标物质和草酸之间的反应产生，含有草酸的洗脱剂和目标物质。

56. 发明专利

JP2013101008A Treatment method and treatment device for radioactive cesium and radioactive strontium contained substance 审中-公开
标题翻译：用于放射性硒和放射性锶含有物质的处理方法和处理装置
公开(公告)号：JP2013101008A
公开(公告)日：2013-05-23
申请号：JP2011244091
申请日：2011-11-08
申请人： Toshiba Corp , 株式会社東芝
发明人： MIKURA MICHITAKA , HARUGUCHI YOSHIKO , OMURA TSUNEO , AKAI YOSHIE , YAMASHITA TAKEO , SUGIMORI TOSHIAKI , MIYAMOTO MASAYA
IPC分类号： G21F9/28 , G21F9/08
摘要： PROBLEM TO BE SOLVED: To easily and efficiently remove radioactive cesium and radioactive strontium from a substance such as soil or mud contaminated by the radioactive cesium and the radioactive strontium.SOLUTION: An organic substance from which cesium and strontium is selectively extractable is brought into contact with a substance containing radioactive cesium and radioactive strontium. Then, at least supercritical carbon dioxide is supplied to and brought into contact with at least the organic substance, and the organic substance is dissolved in the supercritical carbon dioxide. Then, the supercritical carbon dioxide is decompressed, and the supercritical carbon dioxide is converted into carbon dioxide gas so that the organic substance can be separated and removed from the supercritical carbon dioxide.
摘要翻译：要解决的问题：从放射性铯和放射性锶污染的土壤或泥土等物质容易有效地清除放射性铯和放射性锶。解决方案：将铯和锶选择性萃取的有机物质与含有放射性铯和放射性锶的物质接触。然后，至少将超临界二氧化碳供给至少与有机物质接触，有机物质溶解在超临界二氧化碳中。然后，将超临界二氧化碳减压，将超临界二氧化碳转化成二氧化碳，使有机物质从超临界二氧化碳中分离除去。版权所有（C）2013，JPO＆INPIT

57. 发明专利

JP2013002943A Nuclear reactor operation method and nuclear reactor control apparatus 有权
标题翻译：核反应堆运行方法和核反应堆控制装置
公开(公告)号：JP2013002943A
公开(公告)日：2013-01-07
申请号：JP2011134091
申请日：2011-06-16
申请人： Toshiba Corp , 株式会社東芝
发明人： KIKUCHI TSUKASA , YOSHIOKA KENICHI , MIKURA MICHITAKA , MATSUYAMA KANAE
IPC分类号： G21C7/24
CPC分类号： Y02E30/31 , Y02E30/39
摘要： PROBLEM TO BE SOLVED: To suppress a generation amount of Hf182 in a long-lifetime type Hf control rod including hafnium because the H182 generated when hafnium stays for a long period in a nuclear reactor is a nuclide of a long half-life period (9×10years) and it with a daughter nuclide Ta182 emitting high energy γ-ray (1121.3 kev) causes a permanent equilibrium.SOLUTION: In an operation method of a nuclear reactor having multiple long-lifetime type Hf control rods 1 of whose material includes hafnium, concerning the multiple long-lifetime type Hf control rods 1, a part of them are all pulled out because of attenuation of Hf181 which is a precursor of H182 in an intermediate period of a reactor cycle which corresponds to a period starting from a time when a predetermined period has elapsed from the operation start of the reactor cycle until reaching a prescribed time before the operation end in at least one reactor cycle within a use period of the long-lifetime type Hf control rod 1.
摘要翻译：待解决的问题：为了抑制包括铪的长寿命型Hf控制棒中的Hf182的产生量，因为在核反应堆中长时间保持铪所产生的H182是长半衰期的核素周期（9×10 6 年），与发射高能γ射线（1121.3kev）的子核素Ta182导致永久平衡。解决方案：在具有多种长寿命型Hf控制棒1的材料包括铪的多个长寿命型Hf控制棒1的核反应堆的操作方法中，其一部分全部被拉出，因为在反应器周期的中间期期间是H182的前体的Hf181的衰减，其对应于从从反应器循环的操作开始经过预定时间直到操作结束之前的规定时间为止的时间段在长寿命型Hf控制棒1的使用期内的至少一个反应器循环。版权所有（C）2013，JPO＆INPIT

58. 发明专利

JP2012225663A Quantitative analysis method of plutonium 审中-公开
标题翻译：钚的定量分析方法
公开(公告)号：JP2012225663A
公开(公告)日：2012-11-15
申请号：JP2011090701
申请日：2011-04-15
申请人： Toshiba Corp , 株式会社東芝
发明人： YAMASHITA TAKEO , MIKURA MICHITAKA , KUROSAWA SETSUMI , MURATA EIICHI , MATSUYAMA KANAE , HARUGUCHI YOSHIKO , SAKURAI JIRO , HIROSE EMIKO
IPC分类号： G01T1/167
摘要： PROBLEM TO BE SOLVED: To provide Pu (plutonium) quantitative analysis method capable of quantitatively analyzing Pu by using radiation measurement such as α-ray spectrometry even in an analysis target sample solution containing much impurity elements such as Ca interrupting α-ray measurement.SOLUTION: The Pu quantitative analysis method for quantitatively analyzing Pu in an analysis target sample solution 10 includes: an iron hydroxide coprecipitation step S101 for generating iron hydroxide coprecipitate 12 containing a rare earth element by adding rare earth compound and iron compound to the analysis target sample solution 10; a rare earth fluoride coprecipitation step S104 for generating rare earth fluoride coprecipitate 15 by adding fluoride to an iron hydroxide coprecipitate solution 13 obtained by dissolving the iron hydroxide coprecipitate 12; and a radiation measurement step S107 for quantitatively analyzing Pu by radiation measurement of a measuring sample 16 prepared from the rare earth fluoride coprecipitate 15.
摘要翻译：要解决的问题：为了提供能够通过使用诸如α射线光谱法的辐射测量来定量分析Pu的Pu（钚）定量分析方法，即使在含有大量杂质元素如Ca中断α-射线的分析目标样品溶液中测量。解决方案：用于在分析对象样品溶液10中定量分析Pu的Pu定量分析方法包括：通过向稀土化合物和铁化合物添加含有稀土元素的氢氧化铁共沉淀物12的氢氧化铁共沉淀步骤S101，分析目标样品溶液10; 稀土氟化物共沉淀步骤S104，用于通过将氟化氢沉淀物12溶解得到的氢氧化铁共沉淀溶液13中加入氟化物来生成稀土氟化物共沉淀物15; 以及辐射测量步骤S107，用于通过由稀土氟化物共沉淀物15制备的测量样品16的辐射测量来定量分析Pu。（C）2013，JPO和INPIT

59. 发明专利

JP2012150044A Method and device for analyzing nuclide in reactor water 审中-公开
标题翻译：用于分析反应器水中的核素的方法和装置
公开(公告)号：JP2012150044A
公开(公告)日：2012-08-09
申请号：JP2011009794
申请日：2011-01-20
申请人： Toshiba Corp , 株式会社東芝
发明人： MURATA EIICHI , MIKURA MICHITAKA , YAMASHITA TAKEO , OBATA MASAMICHI
IPC分类号： G01N1/28 , G01N1/10 , G01N31/00 , G01T1/167 , G21C17/02
摘要： PROBLEM TO BE SOLVED: To provide a nuclide analysis technology for reactor water which improves accuracy in quantifying radioactive nuclide included in reactor water.SOLUTION: The nuclide analysis technology for reactor water involves steps of: collecting reactor water and passing it through a filter (S11); heating the filter in which nuclide have been collected, with alkali hydroxide and alkaline nitrate (S15); dissolving a product from the heating step into water (S16); and separating a first filtrate in which at least radioactive chlorine and radioactive iodine are dissolved, and a first precipitate which is insoluble to the water (S17).
摘要翻译：要解决的问题：为反应堆水提供核素分析技术，提高定量反应堆水中放射性核素的准确性。解决方案：反应堆水的核素分析技术包括以下步骤：收集反应堆水并通过过滤器（S11）; 用碱性氢氧化物和碱性硝酸盐加热其中已经收集了核素的过滤器（S15）; 将产品从加热步骤溶解到水中（S16）; 并分离其中至少溶解有放射性氯和放射性碘的第一滤液和不溶于水的第一沉淀物（S17）。版权所有（C）2012，JPO＆INPIT

60. 发明专利

JP2012149168A Method of treating waste ion exchange resin containing chromium 审中-公开
标题翻译：处理含有铬离子交换树脂的方法
公开(公告)号：JP2012149168A
公开(公告)日：2012-08-09
申请号：JP2011008802
申请日：2011-01-19
申请人： Toshiba Corp , 株式会社東芝
发明人： SATO TATSUAKI , YASUMURA KEIJIRO , SHOJI YUICHI , HARUGUCHI YOSHIKO , MIKURA MICHITAKA , FUKUSHIMA TADASHI
IPC分类号： C08J11/12 , B09B3/00 , C01G37/033 , F23G5/027 , G21F9/30
CPC分类号： Y02W30/703
摘要： PROBLEM TO BE SOLVED: To reduce the amount of hexavalent chromium contained in a combustion residue by a simple method when a waste ion exchange resin having a relatively large amount of chromium adsorbed thereon or contained therein is burnt and then solidified with cement especially at a nuclear facility.SOLUTION: A method of treating the waste ion exchange resin containing the chromium includes: a step of carbonizing the waste ion exchange resin; and a step of solidifying with the cement, a residue generated after the carbonization.

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