子分类：
- G21G2001/0015： ..氟
- G21G2001/0021： ..镓
- G21G2001/0026： ..砷
- G21G2001/0031： ..铷
- G21G2001/0036： ..钼
- G21G2001/0042： ..锝
- G21G2001/0047： ..铑
- G21G2001/0052： ..钯
- G21G2001/0057： ..铟
- G21G2001/0063： ..碘
- G21G2001/0068： ..铯
- G21G2001/0073： ..铼
- G21G2001/0078： ..铊
- G21G2001/0084： ..铋
- G21G2001/0089： ..锕
- G21G2001/0094： ..其他同位素不提供在上面列出的组
| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 181 | METHOD AND APPARATUS FOR THE RECOVERY OF RADIOACTIVE NUCLIDES FROM SPENT RESIN MATERIALS | EP14802011.8 | 2014-11-19 | EP3221048B1 | 2018-10-10 | STROHMER, Franz; SEMPERE BELDA, Luis |
| A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method. | ||||||
| 182 | YTTRIUM-90 PRODUCTION SYSTEM AND METHOD | EP16818624.5 | 2016-06-28 | EP3317885A1 | 2018-05-09 | TSANG, Francis, Yu-Hei |
| A method of producing the therapeutic medical isotope yttrium-90 (Y-90) is provided that includes providing a zirconium target composed at least partially of Zr-90, directing an electron beam onto a high-Z converter to generate a neutron beam having a maximum energy level of 12.1 MeV, and directing the neutron beam onto the zirconium target to isotopically convert at least a portion of the Zr-90 to the Y-90 medical isotope. | ||||||
| 183 | SOLUTION TARGET FOR CYCLOTRON PRODUCTION OF RADIOMETALS | EP15793539 | 2015-05-15 | EP3142709A4 | 2017-12-20 | DEGRADO TIMOTHY R; PANDEY MUKESH; BYRNE JOHN |
| Methods of producing and isolating 68Ga, 89Zr, 64Cu, 63Zn, 86Y, 61Cu, 99mTc, 45Ti, 13N, 52Mn, or 44Sc and solution targets for use in the methods are disclosed. The methods of producing 68Ga, 89Zr, 64Cu, 63Zn, 86Y, 61Cu, 99mTc, 45Ti, 13N, 52Mn, or 44Sc include irradiating a closed target system with a proton beam. The closed target system can include a solution target. The methods of producing isolated 68Ga, 89Zr, 64Cu, 63Zn, 86Y, 61CU, 99mTC, 45-Ti, 52Mn, or 44Sc by ion exchange chromatography. An example solution target includes a target body including a target cavity for receiving the target material; a housing defining a passageway for directing a particle beam at the target cavity; a target window for covering an opening of the target cavity; and a coolant gas flow path disposed in the passageway upstream of the target window. | ||||||
| 184 | PROCESS FOR PRODUCING GALLIUM-68 THROUGH THE IRRADIATION OF A SOLUTION TARGET | EP15170854.2 | 2015-06-05 | EP3101660B1 | 2017-08-09 | Alves, Vitor H.; Alves, Francisco; Abrunhosa, Antero J. |
| 185 | HIGH PURITY SN-117M COMPOSITIONS AND METHODS OF PREPARING SAME | EP15779052.8 | 2015-08-04 | EP3178088A1 | 2017-06-14 | ST. GEORGE, George; CRUMP, Druce; SIMON, Jaime; STEVENSON, Nigel, R. |
| A method of purifying a high specific activity Sn-117m composition is provided that includes extracting an iodide complex of Sn-117m with an organic solvent from an acidic aqueous cadmium solution comprising a dissolved irradiated cadmium target, an acid, and a source of iodide. The organic solvent layer comprising the iodide complex of Sn-117m is substantially reduced in cadmium content. The Sn-117m may be back extracted into an aqueous solution. | ||||||
| 186 | PRODUCTION OF 43SC RADIONUCLIDE AND RADIOPHARMACEUTICALS THEREOF FOR USE IN POSITRON EMISSION TOMOGRAPHY | EP15720728.3 | 2015-05-07 | EP3143626A1 | 2017-03-22 | VAN DER MEULEN, Nicholas; TÜRLER, Andreas; BUNKA, Maruta |
| The radionuclide 43Sc is produced at commercially significant yields and at specific activities and radionuclidic purities which are suitable for use in radiodiagnostic agents including imaging agents. In a method, a solid target having an isotopically enriched target layer prepared on an inert substrate is positioned in a specially configured target holder and irradiated with a charged-particle beam of protons or deuterons. The beam is generated using an accelerator such as a biomedical cyclotron at energies ranging from 3 to about 22 MeV. The method includes the use of three different nuclear reactions: a) irradiation of enriched 43Ca targets with protons to generate the radionuclide 43Scin the nuclear reaction 43Ca (p,n)43Sc, b) irradiation of enriched 42Ca targets with deuterons to generate the radionuclide 43Sc in the nuclear reaction 42Ca(d,n)43Sc, and c) irradiation of enriched 46Ti targets with protons to generate the radionuclide 43Sc in the nuclear reaction 46Ti (p,a)43Sc. | ||||||
| 187 | SOLUTION TARGET FOR CYCLOTRON PRODUCTION OF RADIOMETALS | EP15793539.6 | 2015-05-15 | EP3142709A2 | 2017-03-22 | DEGRADO, Timothy, R.; PANDEY, Mukesh; BYRNE, John |
| Methods of producing and isolating 68Ga, 89Zr, 64Cu, 63Zn, 86Y, 61Cu, 99mTc, 45Ti, 13N, 52Mn, or 44Sc and solution targets for use in the methods are disclosed. The methods of producing 68Ga, 89Zr, 64Cu, 63Zn, 86Y, 61Cu, 99mTc, 45Ti, 13N, 52Mn, or 44Sc include irradiating a closed target system with a proton beam. The closed target system can include a solution target. The methods of producing isolated 68Ga, 89Zr, 64Cu, 63Zn, 86Y, 61CU, 99mTC, 45-Ti, 52Mn, or 44Sc by ion exchange chromatography. An example solution target includes a target body including a target cavity for receiving the target material; a housing defining a passageway for directing a particle beam at the target cavity; a target window for covering an opening of the target cavity; and a coolant gas flow path disposed in the passageway upstream of the target window. | ||||||
| 188 | METHOD AND DEVICE FOR SEPARATING TECHNETIUM FROM TECHNETIUM-CONTAINING MOLYBDENUM AND PURIFYING SAME, AND METHOD AND DEVICE FOR RECOVERING MOLYBDENUM | EP10857531 | 2010-09-22 | EP2620950A4 | 2017-03-22 | TAGAMI KEIKO; UCHIDA SHIGEO; NAGATSU KOUTARO; FUJIBAYASHI YASUHISA |
| 189 | PROCESS FOR PRODUCING GALLIUM-68 THROUGH THE IRRADIATION OF A SOLUTION TARGET | EP15170854.2 | 2015-06-05 | EP3101660A1 | 2016-12-07 | Alves, Vitor H.; Alves, Francisco; Abrunhosa, Antero J. |
The present invention relates to a process for purifying and concentrating 68Ga isotope produced by the irradiation with an accelerated particle beam of a 68Zn target in solution. The process according to the invention allows for the production of pure and concentrated 68Ga isotope in hydrochloric acid solution. The present invention also relates to a disposable cassette (500) suitable to perform the steps of purification and concentration of the process.
|
||||||
| 190 | PURIFICATION APPARATUS FOR MO-99 | EP15185983.2 | 2011-08-02 | EP2993669A1 | 2016-03-09 | BARBOSA, Luis A.M.M. |
A process for purifying Mo-99 from an acidic solution obtained by dissolving an irradiated solid target comprising uranium in an acidic medium, or from an acidic solution comprising uranium and which has previously been irradiated in a nuclear reactor, or from an acidic solution comprising uranium and which has been used as reactor fuel in a homogeneous reactor, the process comprising contacting the acidic solution with an adsorbent comprising a zirconium oxide, zirconium hydroxide, zirconium alkoxide, zirconium halide and/or zirconium oxide halide, and eluting the Mo-99 from the adsorbent using a solution of a strong base, the eluate then being subjected to a subsequent purification process involving an alkaline-based Mo-99 chromatographic recovery step on an anion exchange material. Also provided is apparatus for carrying out the process.
|
||||||
| 191 | QUASI-NEUTRAL PLASMA GENERATION OF RADIOISOTOPES | EP14724247.3 | 2014-04-01 | EP2981514A1 | 2016-02-10 | Haaland, Peter; Papadopoulos, Konstantinos; Zigler, Arie |
| Methods and apparatus for synthesizing radiochemical compounds are provided. The methods include generating a quasi-neutral plasma jet, and directing the plasma jet onto a radionuclide precursor to provide one or more radionuclides. The radionuclides can be used to prepare radiolabeled compounds, such as radiolabeled biomarkers. | ||||||
| 192 | Verfahren zur Herstellung trägerfreier hochreiner 177Lu-Verbindungen sowie trägerfreie 177Lu-Verbindungen | EP12163203.8 | 2012-04-04 | EP2546839B1 | 2015-11-04 | Marx, Sebastian; Harfensteller, Mark; Zhernosekov, Konstantin; Nikula, Tuomo |
| 193 | Burnable poison materials and apparatuses for nuclear reactors and methods of using the same | EP10160137.5 | 2010-04-16 | EP2242063B1 | 2015-10-07 | Russell II, William Earl; Monetta, Christopher J.; Trosman, Lukas |
| 194 | METHODS AND APPARATUS FOR SELECTIVE GASEOUS EXTRACTION OF MOLYBDENUM-99 AND OTHER FISSION PRODUCT RADIOISOTOPES | EP11764369.2 | 2011-06-08 | EP2580763B1 | 2015-07-22 | BROWN, Lloyd, C. |
| 195 | METHODS FOR PRODUCING Cu-67 RADIOISOTOPE WITH USE OF A CERAMIC CAPSULE FOR MEDICAL APPLICATIONS | EP12835932 | 2012-08-23 | EP2760793A4 | 2015-05-20 | EHST DAVID A; WILLIT JAMES L |
| The present invention provides a method for producing Cu67 radioisotope suitable for use in medical applications. The method comprises irradiating a metallic zinc-68 (Zn68) target within a sealed ceramic capsule with a high energy gamma ray beam. After irradiation, the Cu67 is isolated from the Zn68 by any suitable method (e.g. chemical and or physical separation). In a preferred embodiment, the Cu67 is isolated by sublimation of the zinc in a ceramic sublimation tube to afford a copper residue containing Cu67. The Cu67 can be further purified by chemical means. | ||||||
| 196 | METHODS FOR PRODUCING Cu-67 RADIOISOTOPE WITH USE OF A CERAMIC CAPSULE FOR MEDICAL APPLICATIONS | EP12835932.0 | 2012-08-23 | EP2760793A1 | 2014-08-06 | EHST, David, A.; WILLIT, James, L. |
| The present invention provides a method for producing Cu67 radioisotope suitable for use in medical applications. The method comprises irradiating a metallic zinc-68 (Zn68) target within a sealed ceramic capsule with a high energy gamma ray beam. After irradiation, the Cu67 is isolated from the Zn68 by any suitable method (e.g. chemical and or physical separation). In a preferred embodiment, the Cu67 is isolated by sublimation of the zinc in a ceramic sublimation tube to afford a copper residue containing Cu67. The Cu67 can be further purified by chemical means. | ||||||
| 197 | METHOD OF PRODUCING RADIONUCLIDES | EP11711686.3 | 2011-03-10 | EP2545560B1 | 2014-01-22 | JANSEN, David, Randall; KRIJGER, Geert, Cornelis; KOLAR, Zvonimir, Ivica; ZEEVAART, Jan, Rijn |
| 198 | PROCESS AND APPARATUS FOR TREATING A GAS STREAM | EP12702647.4 | 2012-01-11 | EP2663523A1 | 2013-11-20 | BARBOSA, Luis |
| A process of treating hydrogen gas liberated from the acid or alkaline dissolution of a metal is provided. The process comprises a step of passing the liberated hydrogen gas through a reactor containing an oxidizing agent for oxidation of the hydrogen gas into water, followed by a step of regenerating the oxidizing agent. Also provided is an apparatus for carrying out the process, the apparatus comprising a reactor containing the oxidizing agent, wherein the reactor is at least partially immersed in an alumina bath. | ||||||
| 199 | 68 Ga-Generator | EP11176249.8 | 2011-08-02 | EP2439747B1 | 2013-09-18 | Zhernosekov, Konstantin; Nikula, Tuomo |
| 200 | METHOD AND SYSTEM FOR RADIOISOTOPE GENERATION | EP11773575.3 | 2011-08-26 | EP2636042A1 | 2013-09-11 | TOTH, James, J.; SODERQUIST, Chuck, Z.; GREENWOOD, Lawrence, R.; MATTIGOD, Shas, V.; FRYXELL, Glen, E.; O'HARA, Matthew, J. |
| A system and a process for producing selected isotopic daughter products from parent materials characterized by the steps of loading the parent material upon a sorbent having a functional group configured to selectively bind the parent material under designated conditions, generating the selected isotopic daughter products, and eluting said selected isotopic daughter products from the sorbent. In one embodiment, the process also includes the step of passing an eluent formed by the elution step through a second sorbent material that is configured to remove a preselected material from said eluent. In some applications a passage of the material through a third sorbent material after passage through the second sorbent material is also performed. | ||||||
QQ群二维码
意见反馈
意见反馈