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    • 71. 发明申请
    • 製鋼原料用のブリケット及びその製造方法
    • 用于生产原材料的原材料及其制造方法
    • WO2005080614A1
    • 2005-09-01
    • PCT/JP2005/003113
    • 2005-02-25
    • 光洋精工株式会社松田 光馬
    • 松田 光馬
    • C22B1/248
    • C22B1/243C22B1/24C22B1/248C22B7/00Y02P10/212
    •  ショット粕を有効に再利用することができる製鋼原料用のブリケット及びその製造方法を提供する。鉄粉を含む金属粉末とショット玉とで構成されるショット粕に、固形化補助剤を滴下した後、当該ショット粕を圧縮成形する。この圧縮成形したショット粕を乾燥する。また、鉄系金属の研削切粉と油分及び水分を含有する研削液とを含む研削スラッジに、ショット粕を混合して綿状凝集体を得る。この綿状凝集体を圧縮成形して、繊維状の研削切粉が粗せん断され且つ余剰の水分及び油分が除去された脆性成形体を作製する。この脆性成形体に固形化補助剤を含浸させて固形した後、乾燥させる。
    • 作为炼钢原料的煤球能够有效地回收笋渣; 及其制造方法。 将凝固助剂滴入由丸粒和含铁粉末的金属粉末组成的丸渣中,并且将射出的渣滓压缩成型。 将压缩成型的射出渣干燥。 或者,在含有铁基金属的研磨碎片的磨碎污泥和含有油和水的研磨液中混合喷丸,从而得到棉状絮状物。 将棉状絮体压缩成型,从而获得脆性成形体,其中纤维磨屑大致被切割并从中除去多余的水分和油分。 将脆性压块浸渍固化助剂,固化并干燥。
    • 72. 发明申请
    • DETERMINING GAS VOLUME, POROSITY, AND INTRINSIC OXIDATION RATE
    • 确定气体体积,多孔性和内在氧化速率
    • WO2004092690A1
    • 2004-10-28
    • PCT/AU2004/000512
    • 2004-04-16
    • AUSTRALIAN NUCLEAR SCIENCE & TECHNOLOGY ORGANISATIONBENNETT, John, WilliamASKRABA, SretenBOYD, Alan, StanleyGARVIE, Andrew, Mckay
    • BENNETT, John, WilliamASKRABA, SretenBOYD, Alan, StanleyGARVIE, Andrew, Mckay
    • G01F22/02
    • G01N15/0826C22B7/00G01F22/02G01N7/02G01N2015/0873Y02P10/122Y02P10/238
    • The present invention describes a method for measuring the intrinsic oxidation rate of a sample wherein a sample of material is placed in a closable sealable enclosure, the enclosure is closed and sealed, and a first gas pressure is measured in the enclosure. The internal volume of the enclosure is then changed by a known volume and a second gas pressure is measured in the enclosure after said changing as a function of time. It is then determined from said second gas pressure as a function of time whether there is a gas leak from or into said enclosure. Where there is no gas leak, the internal gas volume of the enclosure is determined from the first and second gas pressures and the known volume. The porosity of the sample may then determined from the volume of gas in the enclosure, the volume of the enclosure and the volume occupied by the sample. A change in gaseous oxygen mass in the enclosure is then determined as a function of time and the intrinsic oxidation rate of the sample determined. The invention further describes methods for determining the intrinsic oxidation rate of a plurality of samples, and for determining a spatial distribution of intrinsic oxidation rate within a waste heap, as well as systems for performing the methods of the invention.
    • 本发明描述了一种用于测量样品的固有氧化速率的方法,其中将材料样品放置在可封闭的可密封外壳中,封闭封闭并密封,并且在外壳中测量第一气体压力。 然后将外壳的内部体积改变已知体积,并且在所述改变之后,在时间范围内,在外壳中测量第二气体压力。 然后根据所述第二气体压力作为时间的函数确定是否存在来自或进入所述外壳的气体泄漏。 在没有气体泄漏的情况下,外壳的内部气体体积根据第一和第二气体压力和已知体积确定。 然后可以根据外壳中的气体体积,外壳的体积和样品占据的体积来确定样品的孔隙率。 然后确定外壳中气态氧质量的变化作为时间的函数,并确定样品的固有氧化速率。 本发明还描述了用于确定多个样品的固有氧化速率以及用于确定废物堆内的本征氧化速率的空间分布的方法以及用于执行本发明的方法的系统。
    • 74. 发明申请
    • FLUID EXTRACTION OF METALS AND/OR METALLOIDS
    • 流体萃取金属和/或金属
    • WO1995033541A1
    • 1995-12-14
    • PCT/US1994006450
    • 1994-06-09
    • IDAHO RESEARCH FOUNDATION, INC.
    • IDAHO RESEARCH FOUNDATION, INC.WAI, Chien, M.
    • B01D11/02
    • C02F9/00B01D11/0403B01D11/0407B01D11/0492C02F1/26C02F1/683C02F2101/20C22B3/0005C22B7/00Y02P10/234
    • A method of extracting metalloid and metal species from a solid or liquid material by exposing the material to a supercritical fluid solvent containing a chelating agent is described. The chelating agent forms chelates that are soluble in the supercritical fluid to allow removal of the species from the material. In preferred embodiments, the extraction solvent is supercritical carbon dioxide and the chelating agent is a fluorinated beta -diketone. In especially preferred embodiments the extraction solvent is supercritical carbon dioxide, and the chelating agent comprises a fluorinated beta -diketone and a trialkyl phosphate, or a fluorinated beta -diketone and a trialkylphosphine oxide. Although a trialkyl phosphate can extract lanthanides and actinides from acidic solutions, a binary mixture comprising a fluorinated beta -diketone and a trialkyl phosphate or a trialkylphosphine oxide tends to enhance the extraction efficiencies for actinides and lanthanides. The method provides an environmentally benign process for removing contaminants from industrial waste without using acids or biologically harmful solvents. The method is particularly useful for extracting actinides and lantanides from acidic solutions. The chelate and supercritical fluid can be regenerated, and the contaminant species recovered, to provide an economic, efficient process.
    • 描述了通过将材料暴露于含有螯合剂的超临界流体溶剂中从固体或液体材料中提取准金属和金属物质的方法。 螯合剂形成可溶于超临界流体的螯合物以允许物质从物质中除去。 在优选的实施方案中,提取溶剂是超临界二氧化碳,螯合剂是氟化的β-二酮。 在特别优选的实施方案中,提取溶剂是超临界二氧化碳,螯合剂包括氟化β-二酮和磷酸三烷基酯,或氟化β-二酮和三烷基氧化膦。 尽管磷酸三烷基酯可以从酸性溶液中提取镧系元素和锕系元素,但包含氟化β-二酮和磷酸三烷基酯或三烷基氧化膦的二元混合物倾向于提高锕系元素和镧系元素的提取效率。 该方法提供了一种环境友好的方法,用于在不使用酸或生物有害溶剂的情况下从工业废物中去除污染物。 该方法特别适用于从酸性溶液中提取锕系元素和镧系元素。 可以再生螯合物和超临界流体,回收污染物质,以提供经济,有效的方法。
    • 78. 发明申请
    • ACTINIDE RECYCLING SYSTEM
    • ACTINIDE回收系统
    • WO2018026536A1
    • 2018-02-08
    • PCT/US2017/043121
    • 2017-07-20
    • ELYSIUM INDUSTRIES LTD.
    • SIMPSON, Michael, F.DODSON, AndrewWANGARD, WilliamPHEIL, EdHANSON, Michael
    • C22B26/20C22B26/10G21F9/12C22B15/00
    • C22B60/02C22B7/00C25B1/26C25C3/34C25C7/025G21F9/12G21F9/308Y02P10/212
    • Systems and methods are provided for recycling actinides from molten chloride fuel salts that have been employed as fuel within a molten salt nuclear reactor. The used molten chloride fuel salts can contain soluble fission products (e.g., non-actinide fission products) that contaminate the molten chloride fuel salt mixture, as well as recoverable actinide chlorides. In one aspect, the contaminating non-actinide fission products can be separated from the molten chloride fuel salt mixture. Subsequently, actinide chlorides remaining within the molten fuel salts can be partitioned into a liquid bismuth phase. These actinides can then be re-chlorinated (e.g., oxidized) to strip them out of the liquid bismuth phase and into a clean molten chloride salt mixture that does not contain contaminating non-actinide fission products and that can be pumped back to the nuclear reactor core as fuel.
    • 提供了系统和方法,用于从在熔盐核反应堆内用作燃料的熔融氯化物燃料盐回收act系元素。 所使用的熔融氯化物燃料盐可含有污染熔融氯化物燃料盐混合物的可溶裂变产物(例如非act系元素裂变产物)以及可回收的act系元素氯化物。 在一个方面,污染的非act系元素裂变产物可以从熔融氯化物燃料盐混合物中分离出来。 随后,保留在熔融燃料盐内的act系元素氯化物可以分配成液态铋相。 然后可以将这些act系元素重新氯化(例如氧化)以将它们从液态铋相中除去并且进入不含有污染的非act系元素裂变产物并且可以被泵回到核反应堆的清洁的熔融氯化物盐混合物中 核心作为燃料。