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1. 发明授权

US10480045B2 Selective regeneration of isotope-specific media resins in systems for separation of radioactive isotopes from liquid waste materials 有权
公开(公告)号：US10480045B2
公开(公告)日：2019-11-19
申请号：US15152432
申请日：2016-05-11
申请人： Kurion, Inc.
发明人： Mark S. Denton
IPC分类号： C22B3/00 , C22B3/42 , B01D39/16 , C02F1/42 , G21F9/00 , B01D59/30 , C22B26/20 , G21F9/04 , B01J39/04 , B01J39/18 , C22B7/00 , C22B26/10 , B01J49/60 , G21F9/30 , C02F101/00 , C02F103/34
摘要： Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

2. 发明授权

US09951398B2 Methods for gas-phase thermochromatographic separations of fission and activation products 有权
公开(公告)号：US09951398B2
公开(公告)日：2018-04-24
申请号：US14807463
申请日：2015-07-23
申请人： University of Tennessee Research Foundation
发明人： John D. Auxier, II , Daniel Hanson , Matthew L. Marsh , Howard L. Hall
IPC分类号： A61K9/00 , C22B59/00 , C22B7/00 , G01N30/12 , G21F9/02 , G21F9/04 , G21F9/28 , G01N30/02
CPC分类号： C22B59/00 , C22B7/007 , G01N30/12 , G01N2030/025 , G21F9/02 , G21F9/04 , G21F9/28
摘要： Methods are provided for characterizing samples containing chemical elements such as rare earth elements, actinides, and heavy transition metals by treating the samples to form volatile complexes of the elements (e.g., β-diketonate complexes or other organic ligand complexes of the elements) and then analyzing the complexes, for example, via gas-phase thermochromatography. Also provided are methods for separating and/or recovering such chemical elements. The methods produce less waste and can be performed more rapidly than conventional liquid extraction methods and can provide separated elements of high purity (e.g., 99.9999% purity).

3. 发明授权

US09922742B2 Tritium adsorbent, method for separating tritium in water, and method for regenerating tritium adsorbent 有权
公开(公告)号：US09922742B2
公开(公告)日：2018-03-20
申请号：US15021448
申请日：2014-09-12
申请人： Hideki Koyanaka
发明人： Hideki Koyanaka
IPC分类号： C02F1/42 , G21F9/04 , B01J49/00 , G21F9/12 , B01J20/06 , B01D59/26 , G21F9/06 , B01J20/28 , B01J20/34 , C01B4/00 , B01D15/42 , C02F1/28 , C02F101/00 , C02F103/06 , C02F103/34
CPC分类号： G21F9/12 , B01D15/426 , B01D59/26 , B01J20/06 , B01J20/28033 , B01J20/3433 , B01J20/345 , C01B4/00 , C02F1/281 , C02F2101/006 , C02F2103/06 , C02F2103/34 , C02F2303/16 , G21F9/04 , G21F9/06
摘要： A method of using hydrogen- or lithium-containing manganese oxide having a spinel crystal structure as a tritium adsorbent to trap tritium from tritium-containing water makes it possible to inexpensively separate tritium from water.

4. 发明授权

US09714457B2 Submersible filters for use in separating radioactive isotopes from radioactive waste materials 有权
公开(公告)号：US09714457B2
公开(公告)日：2017-07-25
申请号：US13850890
申请日：2013-03-26
申请人： Kurion, Inc.
发明人： Mark S. Denton , Joshua Mertz , Trevor Zimmerman
IPC分类号： B01D39/16 , C22B3/42 , C02F1/42 , G21F9/00 , B01D59/30 , C22B3/00 , C22B26/20 , G21F9/04 , B01J39/04 , B01J39/18 , C22B7/00 , C22B26/10 , B01J49/60 , G21F9/30 , C02F101/00 , C02F103/34
CPC分类号： C22B3/42 , B01D39/1623 , B01D59/30 , B01D2259/40083 , B01J39/04 , B01J39/18 , B01J49/60 , C02F1/42 , C02F2101/006 , C02F2103/34 , C22B7/006 , C22B23/0461 , C22B26/10 , C22B26/20 , G21F9/007 , G21F9/04 , G21F9/305
摘要： Submersible media filters and submersible columns for use in removing radioactive isotopes and other contaminants from a fluid stream, such as a fluid stream from the primary coolant loop of a nuclear reactor system or a fluid stream from a spent-fuel pool. Generally, these submersible media filters and submersible columns are adapted to be submersed in the fluid stream, and additionally the filters are adapted to be vitrified after use, resulting in a stabilized, non-leaching final waste product with a substantially reduced volume compared to the original filter. In several embodiments, the submersible media filters and submersible columns include isotope-specific media (ISM).

5. 发明授权

US09409147B2 Method for granulation of absorbent and adsorbent granules prepared by the same 有权
标题翻译：用于制备由其制备的吸收剂和吸附剂颗粒的方法
公开(公告)号：US09409147B2
公开(公告)日：2016-08-09
申请号：US14454448
申请日：2014-08-07
申请人： Institute of Nuclear Energy Research Atomic Energy Council, Executive Yuan
发明人： Sheng-Wei Chiang , Kuang-Li Chien , Jen-Chieh Chung , Shih-Che Huang , Chi-Hung Liao , Kou-Min Lin
IPC分类号： B01J23/00 , B01J20/30 , B01J47/00 , B01J20/18 , C02F1/42 , B01J20/10 , B01J20/12 , B01J20/16 , G21F9/12 , G21F9/04 , G21F9/10 , C02F101/00
CPC分类号： B01J20/3021 , B01J20/10 , B01J20/12 , B01J20/165 , B01J20/18 , B01J20/183 , B01J20/3028 , B01J47/018 , C02F1/42 , C02F2101/006 , G21F9/04 , G21F9/10 , G21F9/12
摘要： The present invention relates to a method for granulation of an absorbent and adsorbent granules prepared by the same. The method comprises the steps of blending sodium metasilicate, metakaoline and an inorganic ion exchange material in water to form a slurry; decanting the resulted slurry onto a nylon cloth of 300 to 400 meshes and natural drying at ambient temperature to solidification; then breaking the solidified final product and sieving it by a screen having a mesh size of from 0.2 to 2.5 mm to provide the absorbent granules having excellent absorbability.
摘要翻译：本发明涉及一种由其制备的吸收剂和吸附剂颗粒的造粒方法。该方法包括将偏硅酸钠，偏高岭土和无机离子交换材料混合在水中以形成浆料的步骤; 将得到的浆料倾析到300-400目的尼龙布上，在环境温度下自然干燥固化; 然后通过网眼尺寸为0.2至2.5mm的筛子将固化的最终产品破碎并筛分，以提供具有优异吸收性的吸收剂颗粒。

6. 发明授权

US09023965B2 Nonconjugated conductive polymers for protection against nuclear radiation including radioactive iodine 有权
标题翻译：用于防止核辐射（包括放射性碘）的非共轭导电聚合物
公开(公告)号：US09023965B2
公开(公告)日：2015-05-05
申请号：US13179876
申请日：2011-07-11
申请人： Mrinal Thakur
发明人： Mrinal Thakur
IPC分类号： C08F132/04 , C08F136/06 , C08F136/08 , G21C11/00 , G21F9/04 , G21F9/28 , G21F9/06 , G21F9/12 , C08L21/00 , C08L47/00
CPC分类号： G21F9/04 , C08L21/00 , C08L47/00 , G21F9/06 , G21F9/12 , G21F9/28
摘要： Nonconjugated conductive polymers absorb radioactive iodine, therefore are useful for protection against nuclear radiation. These polymers have at least one double bond per repeat unit. The ratio of the number of double bonds to the total number of bonds along the polymer chain is less than half. Examples of nonconjugated conductive polymers include: cis-1,4-polyisoprene (natural rubber), trans-1,4-polyisoprene (gutta percha), polybutadiene, polydimethyl butadiene, poly(b-pinene), styrene butadiene rubber (SBR), polyalloocimene, polynorbornene and many others. Through interaction with iodine atoms the double bonds in the nonconjugated polymers transform into radical cations leading to a dark color. The iodine atoms remain (immobile) bound to the polymer chain through the charge-transfer interaction, these polymers are very inexpensive and can be easily processed into any shape, structure and size. Therefore, these are useful for protection against nuclear radiation including radioactive iodine. These polymers when used as a thick cover can provide safe storage of nuclear waste materials including spent fuel rods.
摘要翻译：非共轭导电聚合物吸收放射性碘，因此可用于防止核辐射。这些聚合物每个重复单元具有至少一个双键。双键数与沿聚合物链的总键数的比例小于一半。非共轭导电聚合物的实例包括：顺式-1,4-聚异戊二烯（天然橡胶），反式-1,4-聚异戊二烯（gutta percha），聚丁二烯，聚二甲基丁二烯，聚（b-蒎烯），丁苯橡胶（SBR）多烯烃，聚降冰片烯等。通过与碘原子的相互作用，非共轭聚合物中的双键转化成自由基阳离子，导致暗色。碘原子通过电荷转移相互作用而保持（固定）与聚合物链结合，这些聚合物非常便宜，并且可以容易地加工成任何形状，结构和尺寸。因此，这些可用于防止包括放射性碘在内的核辐射。当用作厚盖时，这些聚合物可以提供包括乏燃料棒在内的核废料的安全储存。

7. 发明申请

US20110103538A1 RADIOACTIVE DEBRIS TRAP 有权
标题翻译：放射性碎片捕获
公开(公告)号：US20110103538A1
公开(公告)日：2011-05-05
申请号：US12609026
申请日：2009-10-30
申请人： Franz Ernst Steinmoeller
发明人： Franz Ernst Steinmoeller
IPC分类号： G21F9/04
CPC分类号： G21C19/42 , B01D21/0003 , B01D21/0042 , B01D21/2427 , F22B37/002 , G21C19/307 , G21D1/006 , G21F9/04 , Y02E30/40
摘要： A radioactive debris trap to be installed in a steam generator for removing debris in the primary flow of a nuclear power plant's primary heat transport system. The debris trap includes an outer cylinder and a coaxial inner cylinder both having a top end and a bottom end. A top plate connects the top ends of the outer and inner cylinders. A bottom plate which encloses the trap is connected to the bottom end of the outer cylinder. There is a gap between the bottom end of the inner cylinder and the bottom plate through which primary flow enters a settling chamber located in an annular gap between the outer and inner cylinders. Several small holes are located at the top end of the outer cylinder through which liquid exits the debris trap. A means for fixedly connecting the debris trap to the steam generator is provided on the outer surface of the outer cylinder. Also included is a means for removing the radioactive debris trap from the steam generator without exposing personnel to excessive radiation.
摘要翻译：要安装在蒸汽发生器中的放射性碎片陷阱，用于清除核电厂主要热交换系统主流中的碎屑。碎片捕集器包括外筒和同轴的内筒，两者都具有顶端和底端。顶板连接外筒和内筒的顶端。封闭收集器的底板连接到外筒的底端。在内筒的底端和底板之间存在间隙，主流通过该间隙进入位于外筒和内筒之间的环形间隙中的沉降室。外筒的顶端有几个小孔，液体通过该小孔离开碎屑陷阱。在外筒的外表面上设置有用于将碎屑捕获器固定地连接到蒸汽发生器的装置。还包括用于从蒸汽发生器中除去放射性碎片捕集器的手段，而不会使人员过度辐射。

8. 发明申请

US20100276345A1 APPARATUS FOR TREATING RADIOACTIVE NITRATE WASTE LIQUID 有权
标题翻译：用于处理放射性硝酸盐废液的设备
公开(公告)号：US20100276345A1
公开(公告)日：2010-11-04
申请号：US12811896
申请日：2009-02-06
申请人： Naoki Ogawa , Katsushi Shibata , Kazuhiko Kuroda , Hiromitsu Nagayasu
发明人： Naoki Ogawa , Katsushi Shibata , Kazuhiko Kuroda , Hiromitsu Nagayasu
IPC分类号： G21F9/18 , G21F9/04 , C02F3/30 , C02F11/00
CPC分类号： C02F3/305 , B01D61/14 , B01D61/58 , B01D2315/06 , C02F1/66 , C02F3/2853 , C02F3/34 , C02F2101/006 , G21F9/18
摘要： An apparatus for treating a radioactive nitrate waste liquid includes: a denitrification tank (12) that accommodates active sludge which adsorbs or takes in a radioactive substance in a nitrate waste liquid (11) containing nitrate and the radioactive substance and in which an anaerobic microorganism that reduces the nitrate to nitrogen gas grows; a reaeration tank (14) that aerates and mixes a denitrification-treated liquid (24) treated in the denitrification tank (12) with the active sludge in which the aerobic microorganism grows; and a sludge dissolution tank (81) that dissolves redundant sludge (26A, 26B) discharged from the denitrification tank (12) and the reaeration tank (14). Acetic peracid (80) is supplied to the sludge dissolution tank (81) to dissolve redundant sludge, a sludge lysate is supplied to the denitrification tank (12) as a carbon source (22), and acetic acid is supplied to the denitrification tank (12).
摘要翻译：一种用于处理放射性硝酸盐废液的设备包括：反硝化池（12），其容纳在含有硝酸盐和放射性物质的硝酸盐废液（11）中吸收或摄取放射性物质的活性污泥，并且其中所述厌氧微生物将硝酸盐还原成氮气生长; 将反硝化池（12）中处理的反硝化处理液（24）充气并混合到需氧微生物生长的活性污泥中的再循环罐（14）和污泥溶解槽（81），其溶解从脱氮槽（12）和再循环槽（14）排出的多余的污泥（26A，26B）。将乙酸（80）供给到污泥溶解槽（81）以溶解多余的污泥，将污泥裂解液作为碳源（22）供给到脱氮槽（12），并将乙酸供给到脱氮槽 12）。

9. 发明授权

US07807058B2 Method and composition for sorbing toxic substances 有权
标题翻译：吸附有毒物质的方法和组成
公开(公告)号：US07807058B2
公开(公告)日：2010-10-05
申请号：US12537907
申请日：2009-08-07
申请人： Joseph Iannicelli
发明人： Joseph Iannicelli
IPC分类号： C02F1/42 , G21F9/04
CPC分类号： B01J20/06 , B01J20/0229 , B01J20/0259 , B01J20/0285 , B01J20/045 , B01J20/08 , B01J20/3078 , B01J20/3085 , B01J2220/4887 , C02F1/281 , C02F2101/20 , C02F2101/22 , C02F2103/06 , C02F2103/10 , C10G25/003 , Y10S95/90 , Y10S210/912 , Y10S210/913 , Y10S210/914
摘要： Toxic substances such as heavy metals are extracted from a medium using a sorbent composition. The sorbent composition is derived by sulfidation of red mud, which contains hydrated ferric oxides derived from the Bayer processing of bauxite ores. Exemplary sulfidizing compounds are H2S, Na2S, K2S, (NH4)2S, and CaSx. The sulfur content typically is from about 0.2 to about 10% above the residual sulfur in the red mud. Sulfidized red mud is an improved sorbent compared to red mud for most of the heavy metals tested (Hg, Cr, Pb, Cu, Zn, Cd, Se, Th, and U). Unlike red mud, sulfidized red mud does not leach naturally contained metals. Sulfidized red mud also prevents leaching of metals when mixed with red mud. Mixtures of sulfidized red mud and red mud are more effective for sorbing other ions, such as As, Co, Mn, and Sr, than sulfidized red mud alone.
摘要翻译：使用吸附剂组合物从介质中提取有毒物质如重金属。吸附剂组合物是通过红泥硫化产生的，该泥浆含有源于铝土矿的拜耳处理的水合氧化铁。示例性硫化化合物是H 2 S，Na 2 S，K 2 S，（NH 4）2 S和CaS x。硫含量通常比红泥中的残留硫高约0.2至约10％。与大部分测试重金属（Hg，Cr，Pb，Cu，Zn，Cd，Se，Th和U）的红泥相比，硫化红泥是一种改进的吸附剂。与红泥不同，硫化红泥不会浸出天然含有的金属。硫化红泥还可防止与红泥混合时金属浸出。硫化红泥和红泥的混合物比单独硫化红泥更有效地吸附其他离子，如As，Co，Mn和Sr。

10. 发明申请

US20100069698A1 TREATMENT OF NUCLEAR SLUDGE 有权
标题翻译：处理核泥沙
公开(公告)号：US20100069698A1
公开(公告)日：2010-03-18
申请号：US12522085
申请日：2007-09-19
申请人： David Deegan , Chris Chapman , Saeed Ismail
发明人： David Deegan , Chris Chapman , Saeed Ismail
IPC分类号： G21F9/04
CPC分类号： C03B5/005 , C03B5/025 , C03B2211/70 , G21F9/16 , G21F9/28 , G21F9/30 , Y02P40/52
摘要： A method for treating nuclear sludge comprising subjecting the nuclear sludge to a plasma treatment in a plasma chamber to melt at least some of the inorganic components of the sludge, wherein the plasma chamber comprises a crucible having a cooled inner surface, this surface cooled sufficiently such that the inorganic components in contact with the inner surface are in a solid state and form a barrier between the part of surface of the crucible with which they are in contact and the molten inorganic components of the sludge.
摘要翻译：一种用于处理核污泥的方法，包括使核污泥在等离子体室中进行等离子体处理，以熔化污泥的至少一些无机成分，其中等离子体室包括具有冷却的内表面的坩埚，该表面充分冷却与内表面接触的无机成分处于固体状态，并在与之接触的坩埚的表面部分和污泥的熔融无机成分之间形成阻挡层。

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