公开(公告)号：US4208377A

公开(公告)日：1980-06-17

申请号：US928026

申请日：1978-07-25

申请人： E. Philip Horwitz ,  George W. Mason

发明人： E. Philip Horwitz ,  George W. Mason

IPC分类号： C01G43/00 ,  C01G56/00 ,  C22B3/38 ,  C22B60/02 ,  C22B60/04 ,  G21C19/46 ,  G21F9/00 ,  C02B1/32

CPC分类号： C22B3/0068 ,  C22B3/0062 ,  C22B3/0067 ,  C22B60/026 ,  C22B60/0291 ,  C22B60/0295 ,  C22B60/04 ,  G21C19/46 ,  G21F9/007 ,  Y02P10/234 ,  Y02W30/883

摘要： A process for rendering actinide values recoverable from sodium carbonate scrub waste solutions containing these and other values along with organic compounds resulting from the radiolytic and hydrolytic degradation of neutral organophosphorous extractants such as tri-n butyl phosphate (TBP) and dihexyl-N,N-diethyl carbamylmethylene phosphonate (DHDECAMP) which have been used in the reprocessing of irradiated nuclear reactor fuels. The scrub waste solution is preferably made acidic with mineral acid, to form a feed solution which is then contacted with a water-immiscible, highly polar organic extractant which selectively extracts the degradation products from the feed solution. The feed solution can then be processed to recover the actinides for storage or recycled back into the high-level waste process stream. The extractant is recycled after stripping the degradation products with a neutral sodium carbonate solution.

摘要翻译： 提供含有这些和其它值的碳酸钠洗涤废液的锕系化合物值的方法，以及由中性有机磷萃取剂如三正丁基磷酸酯（TBP）和二己基-N，N-二甲基甲酰胺的放射和水解降解产生的有机化合物， 二乙基氨基甲酰基亚甲基膦酸酯（DHDECAMP）已被用于辐射核反应堆燃料的后处理。 洗涤废液优选用无机酸酸化，形成进料溶液，然后与进料溶液选择性提取降解产物的与水不混溶的高极性有机萃取剂接触。 然后可以处理进料溶液以回收锕系元素用于储存或循环回到高级废物处理流中。 萃取剂在用中性碳酸钠溶液汽提降解产物后再循环。

公开(公告)号：US4197274A

公开(公告)日：1980-04-08

申请号：US893304

申请日：1978-04-04

申请人： Shinichi Nemoto ,  Satoshi Ikeda ,  Hiroaki Kobayashi ,  Naomi Tsunoda

发明人： Shinichi Nemoto ,  Satoshi Ikeda ,  Hiroaki Kobayashi ,  Naomi Tsunoda

IPC分类号： C22B61/00 ,  C01G56/00 ,  C22B60/04 ,  G21F9/00 ,  G21F9/06

CPC分类号： C01G56/004

摘要： A process for reducing plutonium is provided in which hydrazine is added as a reducing agent to a nitric acid solution of tetravalent plutonium in the presence of active carbon catalyst to thereby reduce tetravalent plutonium into trivalent plutonium.

摘要翻译： 提供了一种还原钚的方法，其中在活性炭催化剂存在下，将肼作为还原剂加入到四价钚的硝酸溶液中，从而将四价钚还原为三价钚。

公开(公告)号：US4159308A

公开(公告)日：1979-06-26

申请号：US695416

申请日：1976-06-14

申请人： Robert J. W. McLaughlin

发明人： Robert J. W. McLaughlin

IPC分类号： C22B3/00 ,  C22B3/04 ,  C22B3/10 ,  C01G56/00

CPC分类号： C22B3/10 ,  Y02P10/234

摘要： The addition of a normally insoluble fluoride to a reaction being a chemical treatment process provides a surprisingly improved rate is dissolution in many cases. Specifically, where the fluoride is added to a reaction using hydrochloric acid or ferric chloride, the yield is more rapid than has previously been shown in the art. The invention is most applicable where the stability constant of the fluoride or fluoride complex of the element to be recovered is higher than that of the cation with which the fluoride is originally associated.

摘要翻译： 在反应中加入通常不溶的氟化物是一种化学处理方法，在许多情况下提供令人惊奇的改善的速率是溶解。 具体地说，当使用盐酸或氯化铁将氟化物加入到反应中时，其产率比本领域已经显示的快得多。 本发明最适用于要回收的元素的氟化物或氟化物络合物的稳定常数高于氟原子最初相关的阳离子的稳定常数。

公开(公告)号：US4092397A

公开(公告)日：1978-05-30

申请号：US667669

申请日：1976-03-17

申请人： Giovanni Brambilla ,  Giacomo Caporali

发明人： Giovanni Brambilla ,  Giacomo Caporali

IPC分类号： G21C19/48 ,  C01G56/00

CPC分类号： G21C19/48 ,  Y02W30/884

摘要： In the recovery of plutonium from irradiated nuclear fuel elements especially those coming from fast nuclear reactors, the improvement consisting in that the spent nuclear fuel elements are subjected to the action of a molten nitrate bath (mixed nitrates of alkali metals or alkaline earth metals), whereafter the plutonium thus obtained is further decomposed in a nitrate bath at a higher temperature, then the plutonium is recovered and a further thermal decomposition of the remaining material at a still higher temperature enables the uranium to be recovered. The recovery of plutonium requires the action of the nitric vapors, the recovery of uranium does not. Molten nitrates can likewise be recovered and recycled.

摘要翻译： 在从被辐射的核燃料元素尤其是来自快核反应堆的核燃料元件中回收钚时，改进之处在于使废核燃料元件受到熔融硝酸盐浴（碱金属或碱土金属的混合硝酸盐）的作用， 此后，如此获得的钚在硝酸盐浴中在较高温度下进一步分解，然后回收钚，并且在更高的温度下进一步热分解剩余的材料使得能够回收铀。 钚的回收需要硝酸蒸气的作用，铀的回收不会。 熔融的硝酸盐同样可以回收和再循环。

公开(公告)号：US4062923A

公开(公告)日：1977-12-13

申请号：US672533

申请日：1976-03-31

申请人： Shingo Takada ,  Ichiro Iwata

发明人： Shingo Takada ,  Ichiro Iwata

IPC分类号： C01G43/04 ,  C01G43/06 ,  C01G56/00

CPC分类号： C01G43/06

摘要： There is provided a process for continuous preparation of uranium tetrafluoride hydrate which comprises the steps of continuously feeding uranous solution and hydrofluoric acid into the lower section of a reaction vessel to produce crystal particles of uranium tetrafluoride hydrate causing the crystal particles to float up and be suspended in the upper section of the reaction vessel by agitation; in which section the crystal particles grow and then precipitating and discharging the thus grown crystal particles from the bottom of the vessel, while causing waste solution to overflow from the top of the vessel. There is also provided an apparatus to accomplish the aforementioned process.

摘要翻译： 提供了一种连续制备四氟化铀水合物的方法，包括将铀溶液和氢氟酸连续供入反应容器的下部，以产生四氟化铀水合物的晶体颗粒，使晶体颗粒浮起并悬浮 在反应容器的上部通过搅拌; 在该部分中，晶体颗粒生长，然后从容器的底部沉淀并排出如此生长的晶体颗粒，同时使废溶液从容器的顶部溢出。 还提供了完成上述过程的装置。

公开(公告)号：US4049769A

公开(公告)日：1977-09-20

申请号：US711748

申请日：1976-08-04

申请人： Maomi Seko ,  Tetsuya Miyake ,  Kohji Inada ,  Kazushi Ochi ,  Tomio Sakamoto

发明人： Maomi Seko ,  Tetsuya Miyake ,  Kohji Inada ,  Kazushi Ochi ,  Tomio Sakamoto

IPC分类号： B01D59/30 ,  B01J31/26 ,  C01G43/00 ,  C22B60/02 ,  C01G56/00

CPC分类号： B01J31/1805 ,  B01D59/30 ,  B01J27/122 ,  B01J27/135 ,  B01J31/0202 ,  B01J31/0204 ,  B01J31/0208 ,  B01J31/182 ,  B01J31/223 ,  B01J31/30 ,  B01J31/38 ,  C01G43/00 ,  C22B60/0265 ,  B01J2231/62 ,  B01J2231/70 ,  B01J2531/16 ,  B01J2531/46 ,  B01J2531/56 ,  B01J2531/842

摘要： A novel catalyst for isotope exchange reaction between uranium(IV) and uranium(VI) compounds enables acceleration of the reaction rate as much as 3000 times to make industrial separation of uranium isotopes economically possible.

摘要翻译： 铀（Ⅳ）和铀（VI）化合物之间的同位素交换反应的新型催化剂可使反应速率加快3000倍，从而使铀同位素工业分离成为可能。

公开(公告)号：US4024068A

公开(公告)日：1977-05-17

申请号：US561191

申请日：1975-03-24

申请人： Bohuslav Cech ,  Evzen Kaderabek ,  Tomas Hanslik

发明人： Bohuslav Cech ,  Evzen Kaderabek ,  Tomas Hanslik

IPC分类号： C01B6/02 ,  C01G25/00 ,  C22B60/02 ,  C22B60/04 ,  G21C19/36 ,  G21C19/38 ,  G21C19/44 ,  C01G43/00 ,  C01G56/00

CPC分类号： C22B60/04 ,  C22B60/0213 ,  G21C19/38 ,  G21C19/44 ,  Y02W30/882

摘要： A process is provided involving the use of hydrogen for the separation of uranium and plutonium and mixtures thereof, from composite substances and assemblies or mixtures containing metallic and ceramic components where the metallic component is zirconium or a zirconium alloy and the ceramic component contains uranium and/or plutonium.

摘要翻译： 提供了一种涉及使用氢气分离铀和钚及其混合物的方法，其中复合材料和组合物或含有金属组分为锆或锆合金的金属和陶瓷组分的混合物，并且陶瓷组分含有铀和/ 或钚。

公开(公告)号：US4011296A

公开(公告)日：1977-03-08

申请号：US581138

申请日：1975-05-27

申请人： Carl Phillip Ruiz ,  John Paul Peterson, Jr.

发明人： Carl Phillip Ruiz ,  John Paul Peterson, Jr.

IPC分类号： C01G43/06 ,  C01G56/00 ,  G21C19/46 ,  G21F9/00 ,  C01G43/00

CPC分类号： C01G43/066 ,  C01G56/001 ,  G21C19/46 ,  G21F9/007 ,  Y02W30/883

摘要： A process for separately recovering uranium, plutonium and neptunium substantially free of fission products from irradiated nuclear fuel is presented in which the fuel is dissolved in a strong mineral acid forming an aqueous dissolved nuclear fuel solution and treated to separate the uranium, plutonium and neptunium therefrom substantially free of said fission products by the sequential steps of solvent extraction, ion exchange and fluorination. The process has an improvement comprising the addition of a sufficient quantity of an additive of a stable metallic complex to the aqueous dissolved nuclear fuel solution prior to solvent extraction. This achieves improved purity of the separated uranium, plutonium and neptunium.

公开(公告)号：US3976748A

公开(公告)日：1976-08-24

申请号：US401273

申请日：1973-09-27

申请人： Werner Lins

发明人： Werner Lins

IPC分类号： C01G56/00

CPC分类号： C01G56/005 ,  C01P2006/88

摘要： For use as a power source in heart pacers, plutonium dioxide having a naturally-occurring oxygen isotope composition is converted into solid phase PuCl.sub.3 which is subsequently oxidized to form plutonium dioxide of the desired isotope composition by means of water vapor, the oxygen component of which consists essentially of the isotope .sup.16 O. Apparatus suited for this purpose is also described.

摘要翻译： 为了用作心脏药剂中的动力源，具有天然存在的氧同位素组成的钚二氧化物被转化为固相PuCl 3，其随后被氧化以形成所需同位素组成的钚二氧化物，所述水蒸汽的氧成分 基本上由同位素16O组成。 还描述了适合于此目的的装置。

公开(公告)号：US3948735A

公开(公告)日：1976-04-06

申请号：US365917

申请日：1973-06-01

申请人： John A. Hayden ,  Carl E. Plock

发明人： John A. Hayden ,  Carl E. Plock

IPC分类号： C01G56/00 ,  C25C1/22

CPC分类号： C01G56/004

摘要： In this invention a first solution obtained from such as a plutonium/thorium purification process or the like, containing plutonium (Pu) and/or thorium (Th) in such as a low nitric acid (HNO.sub.3) concentration may have the Pu and/or Th separated and concentrated by passing an electrical current from a first solution having disposed therein an anode to a second solution having disposed therein a cathode and separated from the first solution by a cation permeable membrane, the Pu or Th cation permeating the cation membrane and forming an anionic complex within the second solution, and electrical current passage affecting the complex formed to permeate an anion membrane separating the second solution from an adjoining third solution containing disposed therein an anode, thereby effecting separation and concentration of the Pu and/or Th in the third solution.

摘要翻译： 在本发明中，从诸如低硝酸（HNO 3）浓度的含有钚（Pu）和/或钍（Th）的诸如钚/钍纯化方法等获得的第一溶液可以具有Pu和/或 通过使来自其中设置有阳极的第一溶液的电流通过其中设置有阴极的第二溶液并通过阳离子可渗透膜与第一溶液分离而分离并浓缩，Pu或Th阳离子渗透阳离子膜并形成 第二溶液中的阴离子络合物，以及影响复合物的电流通道，所述络合物形成为渗透阴离子膜，所述阴离子膜将第二溶液与包含在其中的阳离子相邻的第三溶液分离，从而在所述第二溶液中分离和浓缩所述第二溶液中的Pu和/ 第三个解决方案。