公开(公告)号：CA2277926C

公开(公告)日：2004-01-20

申请号：CA2277926

申请日：1998-01-28

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： DES CHANE JAQUETTA R ,  BRAY LANE A

IPC: G21G4/08 ,  B01D15/04 ,  B01D59/30 ,  B01J20/22 ,  B01J20/26 ,  B01J41/04 ,  B01J49/00 ,  C01G29/00 ,  C01G30/00 ,  C22B30/06 ,  B01J41/00 ,  G01N30/96

Abstract: A method for separating 213Bi from a solution of radionuclides wherein the solution contains a concentration of the chloride ions and hydrogen ions adjusted to allow the formation of a chloride complex. The solution is then brought into contact with an anion exchange resin, whereupon 213Bi is absorb ed from the solution and adhered onto the anion exchange resin in the chloride complex. Other non-absorbing radionuclides such as 225Ra, 225Ac, and 221Fr, along with HCl are removed from the anion exchange resin with a scrub solution. The 213Bi is removed from the anion exchange resin by washing the anion exchange resin with a stripping solution free of chloride ions and wit h a reduced hydrogen ion concentration which breaks the chloride anionic complex, releasing the 213Bi as a cation. In a preferred embodiment of the present invention, the anion exchange resin is provided as a thin membrane, allowing for extremely rapid adherence and stripping of the 213Bi. A preferr ed stripping solution for purification of 213Bi for use in medical applications includes sodium acetate, pH 5.5. A protein conjugated with bifunctional chelating agents in vivo with the Na0Ac, to receive the 213Bi as it is being released from the anion exchange resin.

公开(公告)号：AT266894T

公开(公告)日：2004-05-15

申请号：AT99935287

申请日：1999-05-26

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： EGOROV OLEG B ,  GRATE JAY W ,  BRAY LANE A

IPC: G21G4/08 ,  G21G4/00

Abstract: The present invention is a method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valves, a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered parent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a series of steps to accomplish the operation. In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution. With the automated generator of the present invention, all solution handling steps necessary to perform a daughter/parent radionuclide separation, e.g. Bi-213 from Ac-225 "cow" solution, are performed in a consistent, enclosed, and remotely operated format. Operator exposure and spread of contamination are greatly minimized compared to the manual generator procedure described in U.S. patent application Ser. No. 08/789,973, now U.S. Pat. No. 5,749,042, herein incorporated by reference. Using 16 mCi of Ac-225 there was no detectable external contamination of the instrument components.

公开(公告)号：CA2277926A1

公开(公告)日：1998-07-30

申请号：CA2277926

申请日：1998-01-28

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： BRAY LANE A ,  DES CHANE JAQUETTA R

IPC: G21G4/08 ,  B01D15/04 ,  B01D59/30 ,  B01J20/22 ,  B01J20/26 ,  B01J41/04 ,  B01J49/00 ,  C01G29/00 ,  C01G30/00 ,  C22B30/06 ,  B01J41/00 ,  G01N30/96

Abstract: A method for separating 213Bi from a solution of radionuclides wherein the solution contains a concentration of the chloride ions and hydrogen ions adjusted to allow the formation of a chloride complex. The solution is then brought into contact with an anion exchange resin, whereupon 213Bi is absorbed from the solution and adhered onto the anion exchange resin in the chloride complex. Other non-absorbing radionuclides such as 225Ra, 225Ac, and 221Fr, along with HCl are removed from the anion exchange resin with a scrub solution. The 213Bi is removed from the anion exchange resin by washing the anion exchange resin with a stripping solution free of chloride ions and with a reduced hydrogen ion concentration which breaks the chloride anionic complex, releasing the 213Bi as a cation. In a preferred embodiment of the present invention, the anion exchange resin is provided as a thin membrane, allowing for extremely rapid adherence and stripping of the 213Bi. A preferred stripping solution for purification of 213Bi for use in medical applications includes sodium acetate, pH 5.5. A protein conjugated with bifunctional chelating agents in vivo with the Na0Ac, to receive the 213Bi as it is being released from the anion exchange resin.

公开(公告)号：CA2154567A1

公开(公告)日：1994-08-04

申请号：CA2154567

申请日：1994-01-21

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： SILVA LAURA J ,  BRAY LANE A

IPC: B01J21/06 ,  B01D61/44 ,  B01J23/10 ,  B01J23/12 ,  B01J23/16 ,  B01J23/38 ,  B01J23/70 ,  B01J37/34 ,  B01J38/48 ,  B01J38/60 ,  B01J38/70 ,  C10G45/04 ,  C10G47/02 ,  C10G49/04 ,  C25B1/00

Abstract: A method of recovering catalyst material from latent catalyst material solids includes: a) combining latent catalyst material solids with a liquid acid anolyte solution and a redox material which is soluble in the acid anolyte solution to form a mixture; b) electrochemically oxidizing the redox material within the mixture into a dissolved oxidant, the oxidant having a potential for oxidation which is effectively higher than that of the latent catalyst material; c) reacting the oxidant with the latent catalyst material to oxidize the latent catalyst material into at least one oxidized catalyst species which is soluble within the mixture and to reduce the oxidant back into dissolved redox material; and d) recovering catalyst material from the oxidized catalyst species of the mixture. The invention is expected to be particularly useful in recovering spent catalyst material from petroleum hydroprocessing reaction waste products having adhered sulfides, carbon, hydrocarbons, and undesired metals, and as well as in other industrial applications.

公开(公告)号：AU6046398A

公开(公告)日：1998-08-18

申请号：AU6046398

申请日：1998-01-28

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： BRAY LANE A ,  CHANE JAQUETTA R DES

IPC: G21G4/08 ,  B01D15/04 ,  B01D59/30 ,  B01J20/22 ,  B01J20/26 ,  B01J41/04 ,  B01J49/00 ,  C01G29/00 ,  C01G30/00 ,  C22B30/06 ,  B01J41/00 ,  G01N30/96

公开(公告)号：CA2333356C

公开(公告)日：2009-08-25

申请号：CA2333356

申请日：1999-05-26

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： BRAY LANE A ,  GRATE JAY W ,  EGOROV OLEG B

IPC: G21G4/00 ,  G21G4/08

Abstract: The present invention is a method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valves, a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered parent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a series of steps to accomplish the operation. In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution. With the automated generator of the present invention, all solution handling steps necessary to perform a daughter/parent radionuclide separation, e.g. Bi-213 from Ac-225 "cow" solution, are performed in a consistent, enclosed, and remotely operated format. Operator exposure and spread of contamination are greatly minimized compared to the manual generator procedure described in U. S. patent application 08/789,973 herein incorporated by reference. Using (16) mCi of Ac-225, there was no detectable external contamination of the instrument components.

公开(公告)号：ES2216544T3

公开(公告)日：2004-10-16

申请号：ES99935287

申请日：1999-05-26

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： EGOROV OLEG B ,  GRATE JAY W ,  BRAY LANE A

IPC: G21G4/08 ,  G21G4/00

Abstract: The present invention is a method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valves, a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered parent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a series of steps to accomplish the operation. In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution. With the automated generator of the present invention, all solution handling steps necessary to perform a daughter/parent radionuclide separation, e.g. Bi-213 from Ac-225 "cow" solution, are performed in a consistent, enclosed, and remotely operated format. Operator exposure and spread of contamination are greatly minimized compared to the manual generator procedure described in U.S. patent application Ser. No. 08/789,973, now U.S. Pat. No. 5,749,042, herein incorporated by reference. Using 16 mCi of Ac-225 there was no detectable external contamination of the instrument components.

公开(公告)号：AU5079799A

公开(公告)日：1999-12-13

申请号：AU5079799

申请日：1999-05-26

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： EGOROV OLEG B ,  GRATE JAY W ,  BRAY LANE A

IPC: G21G4/08 ,  G21G4/00

Abstract: The present invention is a method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valves, a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered parent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a series of steps to accomplish the operation. In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution. With the automated generator of the present invention, all solution handling steps necessary to perform a daughter/parent radionuclide separation, e.g. Bi-213 from Ac-225 "cow" solution, are performed in a consistent, enclosed, and remotely operated format. Operator exposure and spread of contamination are greatly minimized compared to the manual generator procedure described in U.S. patent application Ser. No. 08/789,973, now U.S. Pat. No. 5,749,042, herein incorporated by reference. Using 16 mCi of Ac-225 there was no detectable external contamination of the instrument components.

公开(公告)号：CA2333356A1

公开(公告)日：1999-12-02

申请号：CA2333356

申请日：1999-05-26

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： EGOROV OLEG B ,  GRATE JAY W ,  BRAY LANE A

IPC: G21G4/08 ,  G21G4/00

Abstract: The present invention is a method of separating a short-lived daughter isoto pe from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a bi-directional pump and one or more valve s, a solution of the parent isotope is processed to generate two separate solutions, one of which contains the daughter isotope, from which the parent has been removed with a high decontamination factor, and the other solution contains the recovered parent isotope. The process can be repeated on this solution of the parent isotope. The system with the fluid drive and one or more valves is controlled by a program on a microprocessor executing a serie s of steps to accomplish the operation. In one approach, the cow solution is passed through a separation medium that selectively retains the desired daughter isotope, while the parent isotope and the matrix pass through the medium. After washing this medium, the daughter is released from the separation medium using another solution. With the automated generator of th e present invention, all solution handling steps necessary to perform a daughter/parent radionuclide separation, e.g. Bi-213 from Ac-225 "cow" solution, are performed in a consistent, enclosed, and remotely operated format. Operator exposure and spread of contamination are greatly minimized compared to the manual generator procedure described in U.S. patent application 08/789,973 herein incorporated by reference. Using (16) mCi of A c- 225, there was no detectable external contamination of the instrument components.

公开(公告)号：WO9832513A3

公开(公告)日：1998-09-17

申请号：PCT/US9801600

申请日：1998-01-28

Applicant: BATTELLE MEMORIAL INSTITUTE

Inventor： BRAY LANE A ,  DES CHANE JAQUETTA R

IPC: G21G4/08 ,  B01D15/04 ,  B01D59/30 ,  B01J20/22 ,  B01J20/26 ,  B01J41/04 ,  B01J49/00 ,  C01G29/00 ,  C01G30/00 ,  C22B30/06 ,  B01J41/00 ,  G01N30/96

CPC classification number: C01G30/001 ,  C22B3/42 ,  C22B30/06 ,  Y02P10/234

Abstract: A method for separating Bi from a solution of radionuclides wherein the solution contains a concentration of the chloride ions and hydrogen ions adjusted to allow the formation of a chloride complex. The solution is then brought into contact with an anion exchange resin, whereupon Bi is absorbed from the solution and adhered onto the anion exchange resin in the chloride complex. Other non-absorbing radionuclides such as Ra, Ac, and Fr, along with HCl are removed from the anion exchange resin with a scrub solution. The Bi is removed from the anion exchange resin by washing the anion exchange resin with a stripping solution free of chloride ions and with a reduced hydrogen ion concentration which breaks the chloride anionic complex, releasing the Bi as a cation. In a preferred embodiment of the present invention, the anion exchange resin is provided as a thin membrane, allowing for extremely rapid adherence and stripping of the Bi. A preferred stripping solution for purification of Bi for use in medical applications includes sodium acetate, pH 5.5. A protein conjugated with bifunctional chelating agents in vivo with the Na0Ac, to receive the Bi as it is being released from the anion exchange resin. 00000

Abstract translation: 一种从放射性核素溶液中分离Bi的方法，其中溶液含有调节氯离子和氢离子浓度以形成氯化物络合物。 然后使溶液与阴离子交换树脂接触，于是从溶液中吸收Bi并附着到氯化物络合物中的阴离子交换树脂上。 使用洗涤溶液从阴离子交换树脂中除去其它非吸收性放射性核素，例如225Aa，225Ae，和221Ce，以及HCl。 通过用不含氯离子的剥离溶液洗涤阴离子交换树脂和降低氢离子浓度，使阴离子交换树脂从阴离子交换树脂中除去，从而破坏了氯化物阴离子络合物，从而释放出Bi作为阳离子。 在本发明的一个优选实施方案中，阴离子交换树脂被提供为薄膜，允许极快的粘附和剥离。 用于纯化用于医疗应用的Bi的优选剥离溶液包括pH 5.5的乙酸钠。 与NaOAc体内与双功能螯合剂缀合的蛋白质，从阴离子交换树脂中释放出来接受<213> Bi。 00000