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公开(公告)号：US09685250B2
公开(公告)日：2017-06-20
申请号：US14476601
申请日：2014-09-03
发明人： Sung-Hee Jung , Sun Ju Choi , Jong Bum Kim , Jin Ho Moon , Seong Ho Choi , Sang Ei Seo
摘要： A method of preparing radioisotope hybrid nanocomposite particles using a sol-gel reaction, and radioisotope hybrid nanocomposite particles prepared using the same are provided. The method includes preparing a complex precursor using a metal ion and an unshared electron pair reactive compound, growing hybrid nanocomposite particles based on the complex precursor by means of a sol-gel reaction, calcining the nanocomposite particles in the air to remove organic matters present in the nanocomposite particles, and irradiating the nanocomposite particles with neutrons to prepare radioisotope hybrid nanocomposite particles. The radioisotope nanocomposite particles prepared using the method can be used as diagnostic and therapeutic particles in the fields of oil refining, chemistry, cement, agriculture, water resources, environment, ocean, and medicine, and can also be used as a radioisotope tracer for evaluating the risk of nanomaterials.
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公开(公告)号：US09177679B2
公开(公告)日：2015-11-03
申请号：US13026102
申请日：2011-02-11
CPC分类号： G21G1/08 , G21G1/00 , G21G1/10 , G21G2001/0036
摘要： The invention provides a method using accelerators to produce radio-isotopes in high quantities. The method comprises: supplying a “core” of low-enrichment fissile material arranged in a spherical array of LEU combined with water moderator. The array is surrounded by substrates which serve as multipliers and moderators as well as neutron shielding substrates. A flux of neutrons enters the low-enrichment fissile material and causes fissions therein for a time sufficient to generate desired quantities of isotopes from the fissile material. The radio-isotopes are extracted from said fissile material by chemical processing or other means.
摘要翻译： 本发明提供一种使用加速器来大量生产放射性同位素的方法。 该方法包括：提供一种低浓度易裂变材料的“核心”，排列成LEU与水调节剂结合的球形阵列。 该阵列被用作乘法器和调节器以及中子屏蔽衬底的衬底包围。 中子通量进入低浓度易裂变材料，并在其中引起足够的时间，从裂变材料产生所需量的同位素。 通过化学处理或其他手段从所述裂变材料中提取放射性同位素。
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33.发明授权Techniques for on-demand production of medical isotopes such as Mo-99/Tc-99m and radioactive iodine isotopes including I-131 有权用于按需生产医用同位素如Mo-99 / Tc-99m和放射性碘同位素（包括I-131）的技术公开(公告)号：US09047997B2
公开(公告)日：2015-06-02
申请号：US12944634
申请日：2010-11-11
申请人： Francis Yu-Hei Tsang
发明人： Francis Yu-Hei Tsang
CPC分类号： G21G1/08 , G21G1/001 , G21G1/06 , G21G4/02 , G21G2001/0036 , G21G2001/0042 , G21G2001/0063 , G21Y2002/201
摘要： A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material.
摘要翻译： 用于放射性同位素生产的系统在照射室中使用快中子引起的耗尽或天然存在的铀靶的裂变。 通过使遇到目标的中子发生散射或反射以增加每个中子在U-238中引起裂变（n，f）反应的概率，可以提高快速裂变。 U-238可以部署为夹在中子反射材料层之间的层，或者被中子反射材料包围的杆。
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34.发明授权Method for studying a sample of material using a heavy ion induced mass spectrometer source 失效使用重离子诱导质谱仪来研究材料样品的方法
公开(公告)号：US5872824A
公开(公告)日：1999-02-16
申请号：US693507
申请日：1996-08-08
申请人： David P. Fries , James F. Browning
发明人： David P. Fries , James F. Browning
CPC分类号： H05H3/06 , G01N23/005 , G21G1/08 , H01J49/40
摘要： A heavy ion generator is used with a plasma desorption mass spectrometer to provide an appropriate neutron flux in the direction of a fissionable material in order to desorb and ionize large molecules from the material for mass analysis.The heavy ion generator comprises a fissionable material having a high n,f reaction cross section. The heavy ion generator also comprises a pulsed neutron generator that is used to bombard the fissionable material with pulses of neutrons, thereby causing heavy ions to be emitted from the fissionable material. These heavy ions impinge on a material, thereby causing ions to desorb off that material. The ions desorbed off the material pass through a time-of-flight mass analyzer, wherein ions can be measured with masses greater than 25,000 amu.
摘要翻译： 重离子发生器与等离子体解吸质谱仪一起使用，以在可裂变材料的方向上提供适当的中子通量，以从材料中解吸和离子化大分子进行质量分析。 重离子发生器包括具有高n，f反应截面的可裂变材料。 重离子发生器还包括脉冲中子发生器，其用于用中子脉冲轰击可裂变材料，从而导致从可裂变材料发射重离子。 这些重离子撞击材料，从而使离子解吸掉该材料。 脱离材料的离子通过飞行时间质量分析仪，其中可以以大于25,000amu的质量来测量离子。
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35.发明授权Process for the recovery of molybdenum-99 from an irradiated uranium alloy target 失效从辐射铀合金靶材回收钼-99的工艺
公开(公告)号：US4701308A
公开(公告)日：1987-10-20
申请号：US806815
申请日：1985-12-10
申请人： Gerard Koehly , Charles Madic
发明人： Gerard Koehly , Charles Madic
CPC分类号： C22B3/0024 , C01G39/003 , G21C19/46 , G21G1/08 , Y02P10/234 , Y02W30/883
摘要： The invention relates to a process for the recovery of molybdenum-99 from an irradiated uranium alloy target.This process comprises the following stages:(a) dissolving the irradiated uranium alloy target in sulphuric acid,(b) separating the iodine and tellurium present in the thus obtained solution,(c) oxidizing the molybdenum-99 present in the Mo (VI) solution, and(d) extracting the thus oxidized molybdenum-99 with a hydroxamic acid of formula: ##STR1## in which R is a radical chosen from the group including straight or branched-chain alkyl radicals, the phenyl radical, phenyl radicals substituted by at least one alkyl radical, arylalkyl radicals and the cyclohexyl radical and R' is a hydrogen atom or an alkyl radical.The hydroxamic acid can be tri-n-butylacetohydroxamic acid and the molybdenum recovered can be used in a technetium generator for medical purposes.
摘要翻译： 本发明涉及从被照射的铀合金靶中回收钼-99的方法。 该方法包括以下步骤：（a）将照射的铀合金靶材溶解在硫酸中，（b）分离由此得到的溶液中存在的碘和碲，（c）氧化Mo（Ⅵ）中存在的钼-99， 溶液，和（d）用下式的异羟肟酸提取如此氧化的钼-99：其中R是选自直链或支链烷基的基团，苯基，苯基 由至少一个烷基，芳基烷基和环己基取代的基团，R'是氢原子或烷基。 异羟肟酸可以是三正丁基乙酰肟酸，所回收的钼可用于医疗用锝发生器。
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36.发明公开公开(公告)号：US20240212875A1
公开(公告)日：2024-06-27
申请号：US18555534
申请日：2022-04-19
发明人： Jan Rídký , Georg KORN
摘要： The present invention relates to a nuclear target (1), a method for inducing a nuclear reaction and a device capable of inducing nuclear reactions. According to the present invention, the nuclear target (1) is equipped with a hollow (12) into which projectile particles (3) are deposited. In the hollow (12), the projectile particles (3) interact with precursors (21 and/or 22 and/or 23), or projectile particles (3) are elastically scattered on isotopes (4). The nuclear target (1), method, or the device thus provides a more efficient induction of nuclear reactions and provides a higher yield of radioisotope production. In another embodiment, the nuclear target (1) can be used as a means used to nuclear waste transmutation, or as a means of sustainable exothermic nuclear reactions.
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公开(公告)号：US20240120123A1
公开(公告)日：2024-04-11
申请号：US18295045
申请日：2023-04-03
申请人： TEXAS THORIUM LLC
摘要： A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example of the disclosed method includes the steps of providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing a nucleus capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level and generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. In the example, the externally generated proton beam is directed into the vessel such that at least some protons forming the beam will interact with an atom forming a part of the at least one salt contained in the vessel to causing interaction between the externally generated proton beam and the at least one salt contained in the vessel to produce (p, n) reactions resulting in the generation of neutrons within the vessel and an absorption reaction involving the generated neutrons and Thorium within the vessel. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton's interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases. the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.
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公开(公告)号：US11238999B2
公开(公告)日：2022-02-01
申请号：US16434324
申请日：2019-06-07
摘要： 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.
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公开(公告)号：US10784009B1
公开(公告)日：2020-09-22
申请号：US16724509
申请日：2019-12-23
申请人： Texas Thorium, LLC
摘要： A Thorium molten salt energy system is disclosed that includes a proton beam source for producing a proton beam, that can vary between a first energy level and a second energy level of, where the generated proton bean can be directed into a main assembly containing both Thorium-containing molten salt and Thorium fuel rods, each containing an inner Beryllium element and an outer solid Thorium element. The generated proton beam can be shaped and directed to impinge upon Lithium within the molten salt to promote the generation of thermal neutrons and the fission of Uranium within the molten salt. The generated proton beam can also be shaped and directed to impinge upon the Beryllium within the Thorium fuel rods to promote the generation of high energy neutrons.
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公开(公告)号：US20190139665A1
公开(公告)日：2019-05-09
申请号：US16174364
申请日：2018-10-30
申请人： TerraPower, LLC
发明人： Ken Czerwinski , Joshua C. Walter
摘要： Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.
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