首页> 外国专利> Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte

Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte

机译:多孔膜电化学电池,用于从熔融盐电解质中回收铀和超铀

摘要

An improved process and device for the recovery of the minor actinides and the transuranic elements (TRU's) from a molten salt electrolyte. The process involves placing the device, an electrically non-conducting barrier between an anode salt and a cathode salt. The porous barrier allows uranium to diffuse between the anode and cathode, yet slows the diffusion of uranium ions so as to cause depletion of uranium ions in the catholyte. This allows for the eventual preferential deposition of transuranics present in spent nuclear fuel such as Np, Pu, Am, Cm. The device also comprises an uranium oxidation anode. The oxidation anode is solid uranium metal in the form of spent nuclear fuel. The spent fuel is placed in a ferric metal anode basket which serves as the electrical lead or contact between the molten electrolyte and the anodic uranium metal.
机译:用于从熔融盐电解质中回收次the系元素和超铀元素(TRU)的改进方法和装置。该过程包括将器件放置在阳极盐和阴极盐之间的非导电势垒。多孔阻挡层允许铀在阳极和阴极之间扩散,但减慢了铀离子的扩散,从而导致阴极电解液中的铀离子耗尽。这允许最终优先存在于乏核燃料(例如Np,Pu,Am,Cm)中的超铀化合物沉积。该装置还包括铀氧化阳极。氧化阳极是核废料形式的固体铀金属。用过的燃料被放在铁金属阳极篮中,该阳极篮用作电引线或熔融电解质与阳极铀金属之间的接触。

著录项

  • 公开/公告号US7799185B1

    专利类型

  • 公开/公告日2010-09-21

    原文格式PDF

  • 申请/专利权人 JAMES L. WILLIT;

    申请/专利号US20060530573

  • 发明设计人 JAMES L. WILLIT;

    申请日2006-09-11

  • 分类号C25C7/00;C25C7/04;

  • 国家 US

  • 入库时间 2022-08-21 18:50:50

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