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    • 3. 发明授权
    • Method of separating and recovering plutonium and neptunium from
plutonium- and neptunium-containing nitric acid solution
    • 从钚和含containing硝酸溶液中分离回收钚和。。的方法
    • US5476641A
    • 1995-12-19
    • US285514
    • 1994-08-04
    • Akio TodokoroYoshiyuki KiharaTakashi Okada
    • Akio TodokoroYoshiyuki KiharaTakashi Okada
    • B01D15/00B01D15/04G21C19/46G21F9/06G21F9/12C01G56/00
    • G21C19/46G21F9/06G21F9/12Y02W30/883
    • A method of separating and recovering Pu and Np from a Pu- and Np-containing nitric acid solution. The method comprises the steps of subjecting a nitric acid solution containing Pu and Np to valence adjustment by adding a reducing agent consisting of hydroxylamine nitrate and hydrazlne to said nitric acid solution so as to reduce Pu and Np in said nitric acid solution to Pu (III) and Np (IV), respectively; adjusting a nitric acid concentration of said nitric acid solution after said valence adjustment to 6 to 8 M; bringing said nitric acid solution after said nitric acid concentration adjustment into contact with a strong basic anion exchange resin so as to cause Np to be selectively adsorbed by said resin and to separate and recover Pu as a plutonium nitrate solution; and eluting said adsorbed Np (IV) by using diluted nitric acid of 1 M or below so as to recover Np as a neptunium nitrate solution. The valence adjustment step may be carried out by subjecting the Pu- and Np-containing nitric acid solution to electrolytic reduction instead of using the reducing agent.
    • 从含P和Np的硝酸溶液中分离和回收Pu和Np的方法。 该方法包括以下步骤:通过向硝酸溶液中加入由硝酸羟胺和腙组成的还原剂,使含有Pu和Np的硝酸溶液进行价态调节,以将所述硝酸溶液中的Pu和Np还原成Pu )和Np(IV); 在所述化合价调节后将所述硝酸溶液的硝酸浓度调节至6〜8M; 将硝酸浓度调节后的硝酸溶液与强碱性阴离子交换树脂接触,使Np被所述树脂选择性吸附并分离并回收Pu作为硝酸钚溶液; 并通过使用1M或更低的稀硝酸洗脱所述吸附的Np(IV),以便硝酸硝铵溶液回收Np。 化合价调节步骤可以通过使含有Pu-和Np的硝酸溶液进行电解还原来代替使用还原剂来进行。
    • 5. 发明授权
    • Method of recovering uranium and transuranic elements from spent nuclear
fuel
    • 从乏核燃料中回收铀和超铀元素的方法
    • US6033636A
    • 2000-03-07
    • US48342
    • 1998-03-26
    • Akio TodokoroYoshiyuki KiharaTakashi Okada
    • Akio TodokoroYoshiyuki KiharaTakashi Okada
    • C01G56/00C25B1/00G21C19/46G21F9/10C01G43/00C22B60/00
    • C25B1/00C01G56/00G21C19/46Y02W30/883
    • The steps for recovering uranium and transuranic elements are simplified, and the generation of waste solvent and waste materials is suppressed. Spent nuclear fuel is dissolved in nitric acid (S100) and the resulting solution is subjected to electrolytic oxidation so that U, Np, Pu, Am is oxidized to VI using Ce as oxidation catalyst. The solution is cooled, and nitrates of valence VI thereby deposit as crystals and are separated from the mother liquor (S104). The mother liquor is heated and concentrated (S114). The mixed crystalline deposit is dissolved in nitric acid (S106), uranyl nitrate is deposited alone by cooling (S108), and the crystals are separated from the U, Np, Pu, Am mixed solution (S110). The uranyl nitrate is dissolved in nitric acid (S112), and the heated and concentrated mother liquor is added to it to prepare another mixed solution. This mixed solution is then subjected to electrolytic oxidation to oxidize the remaining U, Np, Pu, Am to valence VI, and the solution is cooled so that U, Np, Pu, Am are coprecipitated with uranyl nitrate as crystals, and can be separated from high level radioactive effluent (S118).
    • 回收铀和超铀元素的步骤简化,废溶剂和废料的产生被抑制。 将耗尽的核燃料溶解在硝酸中(S100),并将所得溶液进行电解氧化,以使用Ce作为氧化催化剂将U,Np,Pu,Am氧化成VI。 将溶液冷却,然后将化合价VI的硝酸盐晶体沉积并与母液分离(S104)。 将母液加热浓缩(S114)。 将混合的结晶沉积物溶解在硝酸中(S106),通过冷却单独沉积硝酸铀酰(S108),并将晶体与U,Np,Pu,Am混合溶液(S110)分离。 将硝酸铀酰溶于硝酸(S112)中,加入浓缩的母液制备另一种混合溶液。 然后对该混合溶液进行电解氧化,将剩余的U,Np,Pu,Am氧化为V,将溶液冷却,使U,Np,Pu,Am与硝酸铀酰作为晶体共沉淀,并可分离 来自高放射性废水(S118)。