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序号	专利名	申请号	申请日	公开（公告）号	公开（公告）日	发明人
1	Extraction process	US13878252	2011-10-06	US09991012B2	2018-06-05	Luis A. M. M. Barbosa
A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the acidic solution i), ii) or iii) having been treated to harvest Mo-99, wherein the process comprises contacting the treated acidic solution with an adsorbent comprising ammonium molybdophosphate (AMP). In an embodiment, the AMP is combined with an organic or inorganic polymeric support, for example AMP synthesized within hollow aluminosilicate microspheres (AMP-C).
2	Extraction Process	US13878252	2011-10-06	US20140234186A1	2014-08-21	Luis A.M.M. Barbosa
A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the acidic solution i), ii) or iii) having been treated to harvest Mo-99, wherein the process comprises contacting the treated acidic solution with an adsorbent comprising ammonium molybdophosphate (AMP). In an embodiment, the AMP is combined with an organic or inorganic polymeric support, for example AMP synthesised within hollow aluminosilicate microspheres (AMP-C).
3	Apparatus and method for generating medical isotopes	US13373899	2011-12-05	US20130142296A1	2013-06-06	Gregory Richard Piefer; Thad Alexander Heltemes; Eric Nicholas Van Abel; Ross Francis Radel
An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.
4	Process of recovering strontium, cesium, cerium and rare earth values from radioactive solutions	US26446063	1963-03-11	US3302993A	1967-02-07	BRAY LANE A

5	METHODS AND APPARATUS FOR THE PRODUCTION OF ISOTOPES	US14681835	2015-04-08	US20150332799A1	2015-11-19	Matthew Fox Fritz
A method for producing an isotope of interest includes providing a target including a first isotope of a target element, and bombarding the target with accelerated ions to produce in the target by nuclear reactions between the accelerated ions and the first isotope of the target element: a second isotope of the target element, wherein the second isotope of the target element is the isotope of interest or a radioisotope within a decay chain of the isotope of interest; and transmutation products of a different elemental form than the target element.
6	Methods of producing cesium-131	US12468679	2009-05-19	US08270554B2	2012-09-18	David H. Meikrantz; John R. Snyder
Methods of producing cesium-131. The method comprises dissolving at least one non-irradiated barium source in water or a nitric acid solution to produce a barium target solution. The barium target solution is irradiated with neutron radiation to produce cesium-131, which is removed from the barium target solution. The cesium-131 is complexed with a calixarene compound to separate the cesium-131 from the barium target solution. A liquid:liquid extraction device or extraction column is used to separate the cesium-131 from the barium target solution.
7	METHODS OF PRODUCING CESIUM-131	US12468679	2009-05-19	US20100296616A1	2010-11-25	DAVID H. MEIKRANTZ; JOHN R. SNYDER
Methods of producing cesium-131. The method comprises dissolving at least one non-irradiated barium source in water or a nitric acid solution to produce a barium target solution. The barium target solution is irradiated with neutron radiation to produce cesium-131, which is removed from the barium target solution. The cesium-131 is complexed with a calixarene compound to separate the cesium-131 from the barium target solution. A liquid:liquid extraction device or extraction column is used to separate the cesium-131 from the barium target solution.
8	PROCESS FOR EXTRACTING CS-137 FROM AN ACIDIC SOLUTION	EP11773620.7	2011-10-06	EP2625695B1	2017-07-19	BARBOSA, Luis, A.M.M.
A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the acidic solution i), ii) or iii) having been treated to harvest Mo-99, wherein the process comprises contacting the treated acidic solution with an adsorbent comprising ammonium molybdophosphate (AMP). In an embodiment, the AMP is combined with an organic or inorganic polymeric support, for example AMP synthesised within hollow aluminosilicate microspheres (AMP-C).
9	PROCESS FOR EXTRACTING CS-137 FROM AN ACIDIC SOLUTION	EP11773620.7	2011-10-06	EP2625695A1	2013-08-14	BARBOSA, Luis, A.M.M.
A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the acidic solution i), ii) or iii) having been treated to harvest Mo-99, wherein the process comprises contacting the treated acidic solution with an adsorbent comprising ammonium molybdophosphate (AMP). In an embodiment, the AMP is combined with an organic or inorganic polymeric support, for example AMP synthesised within hollow aluminosilicate microspheres (AMP-C).

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