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1. 发明授权

US4059671A Method for increasing the lifetime of an extraction medium used for reprocessing spent nuclear fuel and/or breeder materials 失效
标题翻译：用于提高用于再加工乏核燃料和/或育种材料的提取介质寿命的方法
公开(公告)号：US4059671A
公开(公告)日：1977-11-22
申请号：US624107
申请日：1975-10-20
申请人： Helmut Schmieder , Ludwig Stieglitz
发明人： Helmut Schmieder , Ludwig Stieglitz
IPC分类号： B01D11/04 , G21C19/46
CPC分类号： G21C19/46 , Y02W30/883
摘要： A method is provided for increasing the lifetime of an extraction medium containing an organophosphorus acid ester and a hydrocarbon and being used for reprocessing spent nuclear fuel and/or breeder materials. Impurities resulting from chemical and/or radiolytic decomposition and interfering compounds of such impurities with radionuclides are removed from the extraction medium by bringing the extraction medium, after use, into intimate contact with an aqueous hydrazine hydrate solution having a concentration of between about 0.1 molar and about 1.0 molar at a temperature between about 20.degree. C to about 75.degree. C. The aqueous hydrazine hydrate solution is then separated from the extraction medium.
摘要翻译：提供了一种提高含有有机磷酸酯和烃的提取介质的寿命的方法，并用于后处理乏核燃料和/或育种材料。通过使萃取介质在使用后与含有约0.1摩尔浓度的水合肼水溶液紧密接触，从萃取介质中除去化学和/或放射分解产生的杂质和这些杂质与放射性核素的干扰化合物的杂质，在约20℃至约75℃的温度下约1.0摩尔。然后将水合肼水溶液与萃取介质分离。

2. 发明授权

US3949049A Method of stripping plutonium from tributyl phosphate solution which contains dibutyl phosphate-plutonium stable complexes 失效
标题翻译：从含磷酸二丁酯稳定配合物的磷酸三丁酯溶液中汽提钚的方法
公开(公告)号：US3949049A
公开(公告)日：1976-04-06
申请号：US233822
申请日：1972-03-10
申请人： Wilhelm Ochsenfeld , Helmut Schmieder
发明人： Wilhelm Ochsenfeld , Helmut Schmieder
IPC分类号： C22B60/02 , C22B60/04 , G21C19/46 , B01D11/04 , C22B61/04
CPC分类号： C22B60/04 , C22B60/026 , G21C19/46 , Y02W30/883
摘要： Fast breeder fuel elements which have been highly burnt-up are reprocessed by extracting uranium and plutonium into an organic solution containing tributyl phosphate. The tributyl phosphate degenerates at least partially into dibutyl phosphate and monobutyl phosphate, which form stable complexes with tetravalent plutonium in the organic solution. This tetravalent plutonium is released from its complexed state and stripped into aqueous phase by contacting the organic solution with an aqueous phase containing tetravalent uranium.
摘要翻译：通过将铀和钚萃取到含有磷酸三丁酯的有机溶液中，对高度燃烧的快速增殖燃料元素进行后处理。磷酸三丁酯至少部分地变成磷酸二丁酯和磷酸一丁酯，其与有机溶液中的四价钚形成稳定的络合物。该四价钚由其络合状态释放并通过使有机溶液与含有四价铀的水相接触而汽提成水相。

3. 发明授权

US4871478A Method of improving the criticality safety in a liquid-liquid extraction process for spent nuclear fuel or breeder reactor materials 失效
标题翻译：提高废核燃料或增殖反应堆材料液液萃取过程中临界安全性的方法
公开(公告)号：US4871478A
公开(公告)日：1989-10-03
申请号：US117848
申请日：1987-11-09
申请人： Georg Petrich , Helmut Schmieder
发明人： Georg Petrich , Helmut Schmieder
IPC分类号： G21C19/42 , G21C19/46 , G21F9/12
CPC分类号： G21F9/125 , G21C19/46 , Y02W30/883
摘要： A process for the extraction of uranium and plutonium from spent nuclear fuels or breeder reactor materials. The spent nuclear fuels or breeder reactor materials are dissolved in nitric acid to provide an aqueous acid solution containing uranium, plutonium, neptunium, other transuranium elements, fission products, corrosion products, activation products and other contamination products. This aqueous acid solution is fed, as an aqueous phase, at a controllable flow rate into a liquid-liquid extraction apparatus also having an organic solvant phase flowing at a controllable rate. The organic phase contains an extraction agent. The temperature of solutions in the extraction apparatus and/or the concentration of the aqueous acid solution before the said aqueous acid solution is fed into the extraction apparatus, is adjusted to satisfy the following inequality: ##EQU1## where T.sub.E =the temperature of the solutions in the extractor (.degree.C.);U.sub.f =the uranium concentration of the feed solution (g/l);Pu.sub.f =the plutonium concentration of the feed solution (g/l);H.sub.f =nitric acid concentration of the feed solution (M/l); ande=base of the natural logarithm system.
摘要翻译：从废核燃料或增殖反应堆材料中提取铀和钚的过程。将废核燃料或增殖反应堆材料溶解在硝酸中以提供含有铀，钚，ium，其他铀元素，裂变产物，腐蚀产物，活化产物和其他污染产物的酸性水溶液。该酸性水溶液作为水相以可控的流速进料到液体 - 液体萃取装置中，该装置也具有以可控速率流动的有机溶剂相。有机相含有提取剂。将提取装置中的溶液的温度和/或酸性水溶液的浓度进料到萃取装置中，以满足以下不等式：TE> 401 +（0.06676 Uf-0.3367 Puf- 327.4 Hf）x ex0.00008179（Uf + Puf）HfxHf-0.9593其中TE =萃取器中溶液的温度（℃）; Uf =进料溶液的铀浓度（g / l）; Puf =进料溶液的钚浓度（g / l）; Hf =进料溶液的硝酸浓度（M / l）; e =自然对数系统的基数。

4. 发明授权

US4246238A Dissolver for removing nuclear fuel materials from fuel element segments 失效
标题翻译：用于从燃料元件段去除核燃料材料的溶解剂
公开(公告)号：US4246238A
公开(公告)日：1981-01-20
申请号：US893777
申请日：1978-04-05
申请人： Hubert Goldacker , Gunter Koch , Helmut Schmieder , Ernst Warnecke , Walter Comper
发明人： Hubert Goldacker , Gunter Koch , Helmut Schmieder , Ernst Warnecke , Walter Comper
IPC分类号： B01D11/02 , G21C19/46 , B01F1/00 , G21F9/30
CPC分类号： B01D11/0219 , G21C19/46 , Y02W30/883
摘要： A dissolver for dissolving nuclear fuel materials out of fuel element segments during reprocessing of irradiated nuclear fuels, the dissolver being made of a material which is a neutron absorber and being composed of a dissolving vessel and a dissolving basket disposed in the vessel to receive such fuel element segments and to permit flow of dissolving fluid therethrough, with the basket being divided into a plurality of individual sections or compartments so as to prevent establishment of a critical state in the dissolver.
摘要翻译：一种溶解器，用于在辐射核燃料的后处理期间将核燃料材料从燃料元件段中溶解，该溶解器由作为中子吸收剂的材料制成，并由设置在该容器中的溶解容器和溶解篮组成以容纳该燃料并且允许溶解流体流过其中，其中篮被分成多个单独的部分或隔室，以便防止在溶解器中建立临界状态。

5. 发明授权

US4212723A Counterflow extraction column 失效
标题翻译：逆流萃取柱
公开(公告)号：US4212723A
公开(公告)日：1980-07-15
申请号：US943979
申请日：1978-09-20
申请人： Helmut Schmieder , Hubert Goldacker , Ernst Warnecke , Manfred Kluth , Reinhard Schlenker
发明人： Helmut Schmieder , Hubert Goldacker , Ernst Warnecke , Manfred Kluth , Reinhard Schlenker
IPC分类号： B01D11/04 , B01D59/24 , B01D59/38 , C22B60/00 , C25B1/00 , G01N25/14 , C25B15/08 , C25B11/03
CPC分类号： G01N25/14 , B01D11/0419 , B01D59/38
摘要： A counterflow extraction column for the liquid-liquid extraction of two phases during simultaneous electrolysis, includes an elongated, upright column tube containing a cathode and an anode. Within the tube, a common chamber defines cathodic zones and anodic zones and is void of separating members between the zones. The common chamber constitutes the anode chamber and the cathode chamber of the column.
摘要翻译：在同时电解期间用于液相萃取两相的逆流萃取塔包括一个含有阴极和阳极的细长直立柱管。在管内，公共室限定阴极区和阳极区，并且在区之间没有分离构件。公共室构成柱的阳极室和阴极室。

6. 发明授权

US4101408A Countercurrent extraction column for liquid-liquid extraction 失效
标题翻译：液 - 液萃取逆流萃取柱
公开(公告)号：US4101408A
公开(公告)日：1978-07-18
申请号：US757062
申请日：1976-12-30
申请人： Helmut Schmieder , Hubert Goldacker , Werner Roos
发明人： Helmut Schmieder , Hubert Goldacker , Werner Roos
IPC分类号： B01D11/04 , B01D59/24 , C01G99/00 , C22B3/02 , C22B60/02 , C25B1/00 , C25C7/00
CPC分类号： C01G99/006 , B01D11/0419 , C22B3/02 , C22B60/026 , C25B1/00 , Y02P10/234
摘要： A countercurrent extraction column for a liquid-liquid extraction of two phases which are insoluble in each other with simultaneous electrolysis. The column comprises an outer tube, an inner tube within the outer tube, with the inner tube dividing the column into an inner anode chamber and an outer cathode chamber which encloses the anode chamber without the use of a diaphragm. A plurality of bores establish communication between the anode chamber and the cathode chamber. An anode is provided in the anode chamber and a cathode is provided in the cathode chamber. A hollow sheet metal cylinder is disposed around the inner tube in the area of the bores between the cathode chamber and the anode chamber. The cylinder acts as a cathode cylinder member and is chargeable in its interior by one of the phases through bores located at the top of the cathode cylinder. Sheet metal strips are attached in a radially inwardly extending manner to the interior surface of the cathode cylinder.
摘要翻译：一种用于液相萃取的逆流提取塔，两相不溶于同时电解。该柱包括外管，外管内管，内管将柱分成内阳极室和外阳极室，其不使用隔膜而封闭阳极室。多个孔在阳极室和阴极室之间建立连通。阳极设置在阳极室中，阴极设置在阴极室中。在阴极室和阳极室之间的孔的区域内围绕内管设置中空的金属板。气缸用作阴极筒构件，并且可通过位于阴极筒顶部的孔之一通过其中一个相位将其内部充电。钣金条以径向向内延伸的方式附接到阴极筒的内表面。

7. 发明授权

US4758313A Process for the improved separation of substances hindering the recovery of the fissionable materials uranium and plutonium and for the improved separation of the fissionable materials 失效
标题翻译：用于改善物质分离的方法，阻碍了可裂变材料铀和钚的回收，并改善了裂变材料的分离
公开(公告)号：US4758313A
公开(公告)日：1988-07-19
申请号：US685660
申请日：1984-12-24
申请人： Helmut Schmieder , Hans J. Bleyl , Zdenek Kolarik , Klaus Ebert
发明人： Helmut Schmieder , Hans J. Bleyl , Zdenek Kolarik , Klaus Ebert
IPC分类号： G21C19/46 , C25C3/34 , C01G43/00 , C01G56/00
CPC分类号： G21C19/46 , Y02W30/883
摘要： A process for the separation of substances hindering the recovery of the fissionable materials uranium and plutonium and for the separation of the fissionable materials to be recovered in a reprocessing process for spent, irradiated nuclear fuel- and/or fertile materials. A second and a third wash of the organic phase is performed for residual ruthenium separation and residual zirconium separation, and there is a repetition of the Pu stripping step with simultaneous electrolytic reduction of Pu(IV) to Pu(III). The second and third wash solutions or the aqueous phase employed for the repetition of plutonium stripping, respectively, each contains a high concentration of product uranyl nitrate. The aqueous run-off from the second and third washes and from the repetition of the Pu stripping step is indirectly fed back into the aqueous fuel solution employed in the first extraction step of the reprocessing method by first feeding these run-offs to an intermediate treatment.
摘要翻译：分离妨碍可裂变材料铀和钚的回收的物质的分离过程，以及在废旧辐射的核燃料和/或肥沃材料的后处理过程中分离待回收的可裂变材料。进行残留钌分离和残余锆分离的有机相的第二次和第三次洗涤，并且重复Pu剥离步骤，同时将Pu（IV）电解还原成Pu（III）。分别用于重复钚汽提的第二和第三洗涤溶液或水相各自含有高浓度的硝酸铀酰产物。从第二次和第三次洗涤出来的含水流出物和从Pu汽提步骤重复的含水流出物间接地反馈到后处理方法的第一提取步骤中使用的含水燃料溶液中，首先将这些排放物送入中间处理。

8. 发明授权

US4741810A Process for reductive plutonium stripping from an organic reprocessing solution into an aqueous, nitric acid solution by use of an electrolytic current 失效
标题翻译：通过使用电解电流从有机再处理溶液中将还原钚汽提到硝酸水溶液中的方法
公开(公告)号：US4741810A
公开(公告)日：1988-05-03
申请号：US681739
申请日：1984-12-14
申请人： Michael Heilgeist , Helmut Schmieder , Klaus Flory
发明人： Michael Heilgeist , Helmut Schmieder , Klaus Flory
IPC分类号： C01G56/00 , C22B3/38 , C22B60/04 , C25B1/00 , G21C19/46
CPC分类号： G21C19/46 , C01G56/001 , C01G56/004 , C22B3/0068 , C22B60/04 , C25B1/00 , Y02P10/234 , Y02W30/883
摘要： A process for reductive plutonium stripping from an organic reprocessing solution into an aqueous, nitric solution by use of an electrolytic current, in which the aqueous solution is free of agents for the stabilization of the reduced valence of the plutonium, a HNO.sub.3 concentration in the range of 0.05 to 1.0 mol/l is established in the aqueous solution, and the reduction of Pu(IV) to Pu(III) is carried out at a maximum temperature of 40.degree. C.
摘要翻译：一种通过使用电解电流从有机后处理溶液中将有机后处理溶液从有机后处理溶液中萃取到硝酸水溶液中的方法，其中水溶液不含稳定钚降低化合价的试剂，HNO 3浓度范围在水溶液中建立0.05〜1.0mol / l，Pu（IV）至Pu（III）的还原最高温度为40℃。

9. 发明授权

US4056482A Method for preparing aqueous, radioactive waste solutions from nuclear plants for solidification 失效
标题翻译：用于制备来自核工业用于固体的水质，放射性废物溶液的方法
公开(公告)号：US4056482A
公开(公告)日：1977-11-01
申请号：US624108
申请日：1975-10-20
申请人： Helmut Schmieder , Reinhard Kroebel
发明人： Helmut Schmieder , Reinhard Kroebel
IPC分类号： C02F1/461 , G21F9/00 , G21F9/06 , G21F9/04
CPC分类号： G21F9/06
摘要： A method is provided for preparing aqueous, radioactive waste solutions, from reprocessing plants for spent nuclear fuel and/or breeder materials and other nuclear plants, for noncontaminating solidification and/or removal of such solutions. The total quantity of the various inorganic and organic substances in the waste solution is reduced by the destruction of nitric acid, nitrates and nitrites and the formation of a waste gas mixture which is practically free of higher nitrous oxides. To bring this about, the radioactive waste solutions are subjected to an electrolysis current at such current densities at the anode and at the cathode that in one process step the substances of the group hydrazine, hydroxylamine, oxalic acid, oxalates, tartaric acid and tartrates are oxidized at the anode and the substances of the group nitric acid, nitrates and nitrites are reduced at the cathode.

10. 发明授权

US4021313A Method for purifying actinides which are in low oxidation states 失效
标题翻译：纯化处于低氧化态的锕系元素的方法
公开(公告)号：US4021313A
公开(公告)日：1977-05-03
申请号：US624106
申请日：1975-10-20
申请人： Helmut Hausberger , Hubert Goldacker , Helmut Schmieder
发明人： Helmut Hausberger , Hubert Goldacker , Helmut Schmieder
IPC分类号： C01G43/00 , C01G56/00 , C01G99/00 , C22B3/00 , C22B3/26 , C22B60/02 , C22B61/00 , C25B1/00 , G21C19/46 , G21F9/00 , G21F9/06 , C25C3/34
CPC分类号： C25B1/00 , C01G43/00 , C01G56/004 , C01G56/008 , C01G99/006 , C22B60/026
摘要： A method is provided for purifying actinides which are present in a low oxidation state in aqueous solution. The actinides are purified of fission products by extracting the actinides from aqueous solution while confining the fission products to the aqueous solution. The actinides that are purified are selected from the group of uranium (IV), neptunium (IV) and plutonium (III). An aqueous nitric acid solution containing the actinides, hydrazine nitrate or hydroxyl ammonium nitrate, as well as fission products is initially subjected to an electrolysis voltage. If Pu (III) is involved, the electrolysis voltage is below the voltage at which oxygen develops at the anode and anodically oxidizes the Pu (III) to Pu (IV). The Pu (IV) which is formed is transferred by means of an organic extraction agent from the aqueous solution to an organic phase. The organic phase is then separated and used for the plutonium recovery process. If U (IV) and/or Np (IV) are involved, the aqueous nitric acid solution is initially subjected to an electrolysis voltage in the vicinity of the voltage at which oxygen develops at the anode or higher to anodically oxidize the U (IV) to U (VI) and the Np (IV) to Np (VI). The U (VI) and/or Np (VI) which is formed is transferred by means of an organic extraction agent from the aqueous phase to the organic phase. The organic phase is then separated and used for the uranium or neptunium recovery process.
摘要翻译：提供了一种用于纯化在水溶液中以低氧化态存在的锕系元素的方法。锕系元素通过从水溶液中提取锕系元素而将裂变产物限制在水溶液中来纯化裂变产物。纯化的锕系选自铀（IV），ium（IV）和钚（III）。含有锕系元素，硝酸肼或硝酸铵的硝酸水溶液以及裂变产物最初经受电解电压。如果涉及Pu（III），则电解电压低于在阳极处产生氧气的电压，并将Pu（III）阳极氧化为Pu（IV）。形成的Pu（IV）通过有机萃取剂从水溶液中转移到有机相中。然后将有机相分离并用于钚回收过程。如果涉及U（IV）和/或Np（IV），则硝酸水溶液最初经受在阳极或更高氧发生的电压附近的电解电压，以阳极氧化U（IV）到U（VI）和Np（IV）到Np（VI）。形成的U（VI）和/或Np（VI）通过有机萃取剂从水相转移到有机相中。然后将有机相分离并用于铀或铀回收过程。

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