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1. 发明专利

JP2007245066A Uranium extracting agent and method for manufacturing the same and method for extracting uranium from scrap uranium by using the same 审中-公开
标题翻译：铀提取剂及其制备方法和使用该方法从铀铀提取铀的方法
公开(公告)号：JP2007245066A
公开(公告)日：2007-09-27
申请号：JP2006074513
申请日：2006-03-17
申请人： Mitsubishi Nuclear Fuel Co Ltd , 三菱原子燃料株式会社
发明人： KONNO MASAYUKI , SHIRATO WATARU , HAMAGUCHI KAZUHIKO
IPC分类号： B01J20/26 , B01J20/30 , B09B3/00 , C08F2/20 , G21F9/06
摘要： PROBLEM TO BE SOLVED: To provide a uranium extracting agent which purifies, separates and recovers uranium from scrap uranium by an extraction chromatography method, makes the elution and depletion of an extractant lower in comparison with the conventional extracting agent, which is used up to now by a method for impregnating a synthetic resin with the extractant to stick the extractant to the surface of the synthetic resin, when uranium is extracted and has high uranium adsorptivity equal to that of the extractant itself, from which adsorbed uranium can be eluted and the used one of which is discarded easily.
SOLUTION: The method for manufacturing the uranium extracting agent comprises the steps of: mixing a skeleton solvent composed of a styrene monomer and acrylic acid or methacrylic acid, a cross-linking agent and a polymerization initiator to prepare a liquid mixture; further mixing the extractant consisting of a monoamide-based solvent in the prepared liquid mixture to prepare a dissolved solution; adding the prepared dissolved solution to a surfactant aqueous solution heated to the temperature of 80-110°C; and agitating the dissolved solution-added surfactant aqueous solution for 1-2 hours while keeping such the temperature to polymerize the skeleton solvent, the extractant and the cross-linking agent and synthesize a granular resin.
COPYRIGHT: (C)2007,JPO&INPIT
摘要翻译：要解决的问题：提供一种通过提取色谱法从废铀中净化，分离和回收铀的铀提取剂，与使用的常规萃取剂相比，萃取剂的洗脱和消耗更低到目前为止，通过萃取剂浸渍合成树脂的方法，将提取剂粘合到合成树脂的表面上，当提取铀并且具有与萃取剂本身相同的铀吸附性时，可以从其中洗脱吸附的铀所使用的一个被容易地丢弃。解决方案：铀提取剂的制备方法包括：将由苯乙烯单体和丙烯酸或甲基丙烯酸组成的骨架溶剂，交联剂和聚合引发剂混合以制备液体混合物; 在制备的液体混合物中进一步混合由单酰胺类溶剂组成的萃取剂以制备溶解溶液; 将制备的溶解溶液加入到加热至80-110℃的表面活性剂水溶液中; 并将溶解的溶液加入的表面活性剂水溶液搅拌1-2小时，同时保持该温度使骨架溶剂，萃取剂和交联剂聚合，并合成颗粒状树脂。版权所有（C）2007，JPO＆INPIT

2. 发明专利

JP2003286022A Method for manufacturing molecular sieve active carbon 有权
标题翻译：制备分子筛活性炭的方法
公开(公告)号：JP2003286022A
公开(公告)日：2003-10-07
申请号：JP2002093820
申请日：2002-03-29
申请人： Mitsubishi Nuclear Fuel Co Ltd , 三菱原子燃料株式会社
发明人： SHIRATO WATARU , HAMAGUCHI KAZUHIKO
IPC分类号： C01B32/336 , B01J20/20 , B01J20/30 , C01B31/10
摘要： PROBLEM TO BE SOLVED: To provide a method for manufacturing molecular sieve active carbon having a medium within a micropore region of pore distribution.
SOLUTION: The method for manufacturing the molecular sieve active carbon has a process in which condensation type tannin powder is dissolved in an aqueous solution of sodium hydroxide or potassium hydroxide or lithium hydroxide of pH 7 to 10 to produce a solution, a process in which the solution is blended with an aldehyde aqueous solution or hexamethylenetetramine, a process in which the obtained mixture solution is heated to produce a stable gelatinized composition, a process in which the gelatinized composition is dried in the temperature range of room temperature to 200°C for 5 to 72 hours, a process in which dried composition is carbonized at 400 to 600°C for 1 to 3 hours in an inert gaseous atmosphere and a process in which activation treatment to the carbonized composition is performed by feeding an inert gas containing carbon dioxide or steam at a rate of 0.1 to 1 mol/min/100 g and heating at 600 to 1,300°C for 0.5 to 2 hours.
COPYRIGHT: (C)2004,JPO
摘要翻译：待解决的问题：提供一种在孔分布的微孔区域内具有介质的分子筛活性炭的制造方法。解决方案：用于制造分子筛活性炭的方法具有将缩合型单宁粉末溶解在pH7至10的氢氧化钠或氢氧化钾或氢氧化锂的水溶液中以产生溶液的方法，方法其中将溶液与醛水溶液或六亚甲基四胺混合，将所得混合溶液加热以产生稳定的糊化组合物的方法，将糊化组合物在室温至200℃的温度范围内干燥的方法在5〜72小时的时间内，将干燥后的组合物在400〜600℃下在惰性气体气氛中碳化1〜3小时的方法，以及对碳化组合物进行活化处理的方法，二氧化碳或蒸汽，速度为0.1〜1mol / min / 100g，在600〜1300℃下加热0.5〜2小时。版权所有（C）2004，JPO

3. 发明专利

JP2004257866A Treating method of waste liquid containing metal element and recovery method of metal element after treatment 审中-公开
公开(公告)号：JP2004257866A
公开(公告)日：2004-09-16
申请号：JP2003049131
申请日：2003-02-26
申请人： Mitsubishi Nuclear Fuel Co Ltd , 三菱原子燃料株式会社
发明人： HAMAGUCHI KAZUHIKO , SHIRATO WATARU
IPC分类号： G21F9/06 , B01J20/24 , C01G43/00 , C01G43/01 , C01G56/00 , C02F1/28 , G21F9/12
摘要： PROBLEM TO BE SOLVED: To provide a treating method of waste liquid containing a metal element capable of reducing a secondary waste generation quantity having a high concentration, and a recovery method of the metal element after treatment capable of recovering as an actinoid oxide having a low salt concentration.
SOLUTION: This treating method of the waste liquid containing the metal element includes a process 11 for neutralizing the waste liquid into a range of 2-3.5 of pH by adding and mixing an alkali solution containing NH
3 or NaOH so as not to generate flocculation precipitate with the waste liquid containing respectively the metal element having the concentration over 1g/l and nitric acid having the concentration over 1N, a process 12 for filling NH
3 type insoluble tannin inside a column, and a process 13 for allowing the neutralized waste liquid to pass through the column in which the NH
3 type insoluble tannin is filled to adsorb the metal element.
COPYRIGHT: (C)2004,JPO&NCIPI

4. 发明专利

JPS6173803A Production of powder mixture composed of uranium dioxide and gadolinium oxide for producing nuclear fuel pellet 失效
标题翻译：生产二氧化铀和氧化OF OF OF OF OF OF OF OF ET ET ET ET ET ET ET ET ET ET ET
公开(公告)号：JPS6173803A
公开(公告)日：1986-04-16
申请号：JP19424484
申请日：1984-09-17
申请人： Mitsubishi Nuclear Fuel Co Ltd
发明人： KAMEI YOSHINOBU , SHIRATO WATARU
IPC分类号： B22F9/24 , G21C3/62
CPC分类号： Y02E30/38
摘要： PURPOSE: To produce a stable powder mixture composed of UO
2 and Gd
2 O
3 as a raw material for nuclear fuel pellets by precipitating the compd. of U and Gd from an aq. nitric acid soln. of U and Gd having a specific concn. and filtering and drying the precipitate then subjecting the same to reduction roasting.
CONSTITUTION: Thoroughly dried U
3 O
8 and Gd
2 O
3 are weighed to a suitable weight so that the content of Gd in UO
2 pellets contg. Gd attains 6wt% in terms of the concn. of Gd
2 O
3 and after the compd. is dissolved in a nitric acid, distilled water is added thereto to prepare the nitric acid soln. of 750°C having 60W110g/l concn. of (U+Gd). Ammonia water is added to the soln. under stir ring to adjust the pH thereof to >8 thereby forming the precipitate consisting of (NH
4 )
2 U
2 O
7 and Gd(OH)
3 . The precipitate is filtered and is dried for 16hr at 150°C and is then roasted at ≥550°C in gaseous N
2 ; in succession, the gaseous atm. is changed over to H
2 and the precipitate is subjected to the hydrogen reduction at ≥550°C, by which the stable powder mixture composed of UO
2 +Gd
2 O
3 is produced.
COPYRIGHT: (C)1986,JPO&Japio
摘要翻译：目的：通过沉淀方法生产由UO2和Gd2O3组成的稳定的粉末混合物作为核燃料颗粒的原料。的U和Gd从一个水平硝酸溶液的U和Gd具有特定的浓度过滤并干燥沉淀物，然后对其进行还原焙烧。构成：将完全干燥的U3O8和Gd2O3称重至合适的重量，使得UO2颗粒中的Gd含量不变。 Gd的浓度达到6wt％。的Gd2O3。溶解在硝酸中，加入蒸馏水制备硝酸溶液。 750℃，60-110g / l浓度。的（U + Gd）。将氨水加入到溶胶中。搅拌环将pH调节至> 8，由此形成由（NH4）2U2O7和Gd（OH）3组成的沉淀物。将沉淀物过滤并在150℃下干燥16小时，然后在气体N 2下在≥550℃下烘烤; 连续地，气态大气。转化为H2，沉淀物在> = 550℃下进行氢还原，由此生成由UO2 + Gd2O3组成的稳定的粉末混合物。

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