子分类：
| 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 | 在超临界CO2介质中制备无机颗粒 | CN200880019641.4 | 2008-04-23 | CN101754800B | 2014-07-23 | B·萨拉; S·维勒曼; J·马祖瓦耶; T·穆勒; N·马斯吉雷兹; D·科特; A·朱贝; P·吉耶米耶 |
| 本发明涉及由无机颗粒前体制备无机颗粒(p)的方法，所述方法包括步骤(E)，该步骤(E)包括使用注射喷嘴将含有溶解和/或分散在溶剂中的所述前体的流体介质(F)注入含有超临界状态的CO2的反应器中，所述注射喷嘴通向超临界CO2所处的比将前体转化为相应的无机物的温度高或与其相等的温度的区域中。本发明还涉及依照该方法获得的颗粒(p)以及其用途。 | ||||||
| 2 | 制备锕系元素的草酸盐和制备锕系元素的化合物的方法 | CN200980151163.7 | 2009-12-17 | CN102256902A | 2011-11-23 | M·贝特朗; S·格朗让; B·库尔托; F·奥热 |
| 本发明涉及制备一种或多种锕系元素的草酸盐的方法，其包括：通过使包含一种或多种所述锕系元素的水溶液与草酸水溶液或草酸盐水溶液接触，以草酸盐颗粒的形式沉淀或共沉淀出所述锕系元素；和收集所得的草酸盐颗粒；所述方法的特征在于，在流化床中进行所述沉淀或共沉淀。本发明还涉及使用所述方法制备一种或多种锕系元素的化合物的方法，所述化合物是氧化物、碳化物、或氮化物。本发明可用于核燃料的加工和再利用。 | ||||||
| 3 | 制备锕系元素的草酸盐和制备锕系元素的化合物的方法 | CN200980151163.7 | 2009-12-17 | CN102256902B | 2014-07-30 | M·贝特朗; S·格朗让; B·库尔托; F·奥热 |
| 本发明涉及制备一种或多种锕系元素的草酸盐的方法，其包括：通过使包含一种或多种所述锕系元素的水溶液与草酸水溶液或草酸盐水溶液接触，以草酸盐颗粒的形式沉淀或共沉淀出所述锕系元素；和收集所得的草酸盐颗粒；所述方法的特征在于，在流化床中进行所述沉淀或共沉淀。本发明还涉及使用所述方法制备一种或多种锕系元素的化合物的方法，所述化合物是氧化物、碳化物、或氮化物。本发明可用于核燃料的加工和再利用。 | ||||||
| 4 | 在超临界CO2介质中制备无机颗粒 | CN200880019641.4 | 2008-04-23 | CN101754800A | 2010-06-23 | B·萨拉; S·维勒曼; J·马祖瓦耶; T·穆勒; N·马斯吉雷兹; D·科特; A·朱贝; P·吉耶米耶 |
| 本发明涉及由无机颗粒前体制备无机颗粒(p)的方法，所述方法包括步骤(E)，该步骤(E)包括使用注射喷嘴将含有溶解和/或分散在溶剂中的所述前体的流体介质(F)注入含有超临界状态的CO2的反应器中，所述注射喷嘴通向超临界CO2所处的比将前体转化为相应的无机物的温度高或与其相等的温度的区域中。本发明还涉及依照该方法获得的颗粒(p)以及其用途。 | ||||||
| 5 | Method of producing halide-free metal and hydroxides | US870070 | 1986-06-03 | US4741894A | 1988-05-03 | Andreas A. Melas |
| Niobium (V) and tantalum (V) halides are converted to Nb.sub.2 O.sub.5 and Ta.sub.2 O.sub.5 that are free of detectable levels of halide in a two step process. In the first step, the metal halide is reacted with an alcohol and with a replacement species, such as ammonia, which reacts with the halide. This produces a metal alkoxide which is soluble and a halide salt of the replacement species which is insoluble in the alcohol and precipitates. After physically separating the alkoxide in alcohol solution from the precipitate, in a second step, the metal alkoxide is hydrolyzed with purified water to produce the oxide. | ||||||
| 6 | Radioisotope fuel material and method | US3790440D | 1971-01-13 | US3790440A | 1974-02-05 | KESHISHIAN V |
| A primary alpha-particle-emitting radioactive fuel material and a method for preparing it so that secondary neutron generation by an alpha-neutron reaction is substantially reduced. Those individual isotopes of oxygen, carbon, nitrogen, silicon, and chlorine which have a threshold for the alpha-neutron reaction greater than the maximum energy of the emitted alpha particles are selected for combination with the alpha-particle-emitting radioactive isotope to give the desired oxides, carbides, nitrides, silicides, and oxychlorides.
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| 7 | Preparation of thoria sols by electrodialysis | US21626662 | 1962-07-18 | US3280011A | 1966-10-18 | O'CONNOR THOMAS L; WALTER JUDA; MCNALLY PAUL H; ROSENBERG NORMANN W |
| 8 | 사용후 핵연료 재처리 및 우라늄-플루토늄 혼합 산화물 제조 방법 | KR1020087028715 | 2007-05-23 | KR101386696B1 | 2014-04-18 | 바론,파스칼; 딘,빈; 메이슨,미쉘; 드랭,프랑소와; 에민,장-뤽 |
| 본 발명은 사용후 핵연료 재처리 및 우라늄-플루토늄 혼합 산화물 제조 방법으로, (a) 질산에 사용후 핵연료를 용해시킨 결과 얻어지는 질산 수용액 속에 함유되어 있는 핵분열 생성물, 아메리슘 및 큐륨으로부터 우라늄과 플루토늄을 분리하는 단계로, 용매상을 이용하여 이 질산 수용액으로부터 우라늄과 플루토늄을 공추출하는 공정을 적어도 하나 포함하는 단계; (b) 공추출된 우라늄과 플루토늄을, 플루토늄과 우라늄을 함유하는 제1 수상, 및 우라늄은 함유하되 플루토늄은 함유하고 있지 않은 제2 수상으로 분리시키는 단계; (c) 제1 수상에 함유되어 있는 플루토늄과 우라늄을 정제하는 단계; 및 (d) 플루토늄과 우라늄을 우라늄-플루토늄 혼합 산화물로 공변환시키는 단계;를 포함하는 것을 특징으로 한다. 응용 : 산화 우라늄 또는 우라늄-플루토늄 혼합 산화물을 기반으로 하는 핵연료의 재처리 핵연료 재처리, 우라늄-플루토늄 혼합 산화물, 공추출, 공변환 | ||||||
| 9 | 사용후 핵연료 재처리 및 우라늄-플루토늄 혼합 산화물 제조 방법 | KR1020087028715 | 2007-05-23 | KR1020090010217A | 2009-01-29 | 바론,파스칼; 딘,빈; 메이슨,미쉘; 드랭,프랑소와; 에민,장-뤽 |
| The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: a) the separation of the uranium and plutonium from the fission products, the americium and the curium that are present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step including at least one operation of coextracting the uranium and plutonium from said solution by a solvent phase; b) the partition of the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) the purification of the plutonium and uranium that are present in the first aqueous phase; and d) a step of coconverting the plutonium and uranium to a mixed uranium/plutonium oxide. Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide. | ||||||
| 10 | Method for preparing a mixture of powdered metal oxides from nitrates thereof in the nuclear industry | US91243 | 1999-03-02 | US06110437A | 2000-08-29 | Gilbert Schall; Sylvie Davied; Robert Faron, deceased |
| A thermal decomposition method useful in the nuclear industry for preparing a powdered mixture of metal oxides having suitable reactivity from nitrates thereof in the form of an aqueous solution or a mixture of solids. According to the method, the solution or the mixture of solids is thermomechanically contacted with a gaseous fluid in the contact area of a reaction chamber, said gaseous fluid being fed into the reaction chamber at the same time as the solution or mixture at a temperature no lower than the decomposition temperature of the nitrates, and having a mechanical energy high enough to generate a fine spray of the solution or a fine dispersion of the solid mixture, and instantly decompose the nitrates. The resulting oxide mixtures may be used to prepare nuclear fuels. | ||||||
| 11 | Process for the electrocatalytic reducing dissolving of refractory compounds of cerium | US754550 | 1996-11-21 | US5830342A | 1998-11-03 | Xavier Machuron-Mandard; Laurent Audubert; Laurent Thouin |
| The invention relates to an electrocatalytic or aero-electrocatalytic process for the reducing dissolving of a refractory compound of cerium such as CeO.sub.2. According to this process, the compound to be dissolved is introduced into an aqueous acid solution, e.g. a sulphuric solution, containing an electrochemical carrier constituted by one of the reducing or oxidizing species of a redox pair, whose redox potential is below +1.25 V/SHE, e.g. a ferric salt, a uranyl salt, molecular iodine or oxygen, and continuous generation and/or regeneration takes place by electrolysis of the reducing species of said redox pair. | ||||||
| 12 | Method for generation of finely divided reactive plutonium oxide powder | US207518 | 1994-03-08 | US5419886A | 1995-05-30 | LeRoy F. Grantham; Richard L. Gay |
| A method of preparing active, sinterable, finely-divided plutonium oxide (PuO.sub.2) powder from plutonium metal is disclosed. The process yields plutonium fissile material which can be easily blended to form a uniformly homogeneous powder for the fabrication of high-quality light water reactor ceramic fuel pellets. Such homogeneous fuels are required to prevent hot spots from developing in a reactor using the fuel. | ||||||
| 13 | Process and apparatus for oxidizing or reducing dissolved substance | US5961 | 1987-01-22 | US4774026A | 1988-09-27 | Takehiko Kitamori; Takashi Nishi; Tetsuo Fukasawa; Haruo Fujimori; Akira Sasahira; Yoshihiro Ozawa; Kazumichi Suzuki; Hideo Yusa |
| A dissolved substance contained in a solution is oxidized or reduced by adding a particulate semiconductor photocatalyst and a water-soluble electron acceptor or donor for the particulate semiconductor photocatalyst to a solution containing a dissolved substance, and irradiating the particulate semiconductor photocatalyst in the solution with an electromagnetic wave having an energy high enough to excite the particulate semiconductor photocatalyst, or by adding a particulate semiconductor photocatalyst and a water-soluble electron acceptor or donor for the particulate semiconductor photocatalyst to a solution containing a dissolved substance and irradiating the particulate semiconductor photocatalyst in the solution with an electromagnetic wave having an energy high enough to excite the particulate semiconductor photocatalyst and having a wavelength outside the absorption wavelength region of a precursor substance capable of producing an oxidation or reduction reaction-inhibiting substance, whereby (1) ions or complexes are converted to simple substances or to ions or compounds with different valencies, and (2) simple substances, ions, complexes or other compounds are separated and recovered or removed by utilizing its actions and effects. | ||||||
| 14 | Method for recovery of actinides from refractory oxides thereof using O.sub. F.sub.2 | US16483 | 1987-02-17 | US4724127A | 1988-02-09 | Larned B. Asprey; Phillip G. Eller |
| Method for recovery of actinides from nuclear waste material containing sintered and other oxides thereof using O.sub.2 F.sub.2 to generate the hexafluorides of the actinides present therein. The fluorinating agent, O.sub.2 F.sub.2, has been observed to perform the above-described tasks at sufficiently low temperatures that there is virtually no damage to the containment vessels. Moreover, the resulting actinide hexafluorides are not destroyed by high temperature reactions with the walls of the reaction vessel. Dioxygen difluoride is readily prepared, stored and transferred to the place of reaction. | ||||||
| 15 | 金属酸化物粉末の調製方法、金属酸化物ペレットの製造方法、これらの方法によって得られる粉末及びペレット、並びにそれらの使用 | JP2016546467 | 2015-01-14 | JP2017507102A | 2017-03-16 | ジュリアン・マルティネ; ファビアン・オーデュベール; ニコラ・クラヴィエ; ニコラ・ダシュー |
| 本発明は、各金属が(III)から(VI)の間の酸化数を有する、少なくとも1種の金属の酸化物の粉末を調製する方法に関する。この方法は、連続的に且つこの順序で:(a)各金属について、前記金属のカチオンの少なくとも1種の塩を含む水溶液の、水酸化物を含む化合物との反応、(b)得られた沈殿物の分離、(c)分離された沈殿物を有機プロトン性極性溶媒と接触させること、(d)真空下での沈殿物の乾燥による有機プロトン性極性溶媒の除去を含む。本発明はまた、少なくとも1種の金属の酸化物のペレットを製造する方法並びにこれらの方法によって得られた粉末及びペレット、並びにそれらの使用に関する。 | ||||||
| 16 | アクチニドシュウ酸塩の生成方法およびアクチニド化合物の生成方法 | JP2015134529 | 2015-07-03 | JP2016000688A | 2016-01-07 | ベルトラン ミュリエル; グランジャン ステファーヌ; クールトー ブリュノ; ウジエ フレデリク |
| 【課題】アクチニドの沈澱、又は、アクチニドの共沈を有し、該沈澱又は共沈が流動層内で行われる少なくとも1種類のアクチニドシュウ酸塩の生成方法の提供。 【解決手段】アクチニドを含む水溶液とシュウ酸またはシュウ酸塩の水溶液との接触によるアクチニドの沈殿またはシュウ酸塩粒子としてのアクチニドの共沈と、-得られたシュウ酸塩粒子の回収と、を有し、沈殿又は共沈が流動層内で行われる少なくとも1種類のアクチニドのシュウ酸塩の生成方法。また、上記の方法を利用した酸化物、炭化物、又は、窒化物タイプのアクチニド化合物の生成方法。 【効果】核燃料の処理およびリサイクルに利用できる。 【選択図】図1 |
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| 17 | 固体シンチレータ、放射線検出器およびＸ線断層写真撮影装置 | JP2011500672 | 2010-02-22 | JP5686724B2 | 2015-03-18 | 福田 幸洋; 幸洋 福田; 大田 博康; 博康 大田; 石井 努; 努 石井; 欣能 舩山 |
| 18 | Mixed extraction agent for the recovery of actinide elements of an acidic solution | JP2004324949 | 2004-11-09 | JP4417227B2 | 2010-02-17 | アンドレイ ユーリエビッチ シャドリン; ボリス ヤコブレビッチ ジリベルマン; イーゴリ ワレンチノビッチ スミルノフ; ワシーリー アレクサンドロビッチ ババイン; ユーリー ステパノビッチ フョードロフ; ワレーリー ニコラエビッチ ロマノフスキー; 正基 小澤 |
| 19 | Mixture extractant recovering actinide element in acidic solution | JP2004324949 | 2004-11-09 | JP2006051488A | 2006-02-23 | OZAWA MASAKI; BABAIN VASILY ALEXANDROVICH; FEDOROV YURY STEPANOVICH; ANDEY YURIEVICH SHADRIN; ROMANOVSKY VALERY NIKOLAEVICH; IGOR VALENTINOVICH SMIRNOV; BORIS YAKOVLEVICH ZILBERMAN |
| <P>PROBLEM TO BE SOLVED: To provide a mixture extractant capable of extracting an actinide element such as U, Pu and a transplutonium element from a radioactive liquid waste in reprocessing a spent nuclear fuel. <P>SOLUTION: The mixture extractant is composed of a solution containing dihexyl-N, N-diethylcarbamoylphosphonate, an organophosphorous extractant with a bidentate coordination, in a polar diluent, using bis-tetrafluoropropyl ether of diethylene glycol as the polar diluent, wherein in a ratio of each component, the extratant with the bidentate coordination is 0.1-1.2 M/L and the diluent is balanced. And alternatively, the mixture extractant is composed of the solution containing octylphenyl-N, N-diisobutylcarbamoylphosphine oxide, the organophosphorous extractant with the bidentate coordination, in the polar diluent, using a mixture of m-nitrobenzotrifluoride(MNBTF) and TBP as the polar diluent, wherein in the ratio of each component, the extractant with the bidentate coordination is 0.1-1.2 M/L, TBP is 0.3-1.1 M/L and MNBTF is balanced. <P>COPYRIGHT: (C)2006,JPO&NCIPI | ||||||
| 20 | Method of recycling pellet scrap of oxide nuclear fuel | JP25176297 | 1997-09-17 | JP3106113B2 | 2000-11-06 | ケンシク キム; ヨンフン キム; ユンホ ジュン; クンウ ソン |
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