An advanced hybrid reprocessing system based on UF6 volatilization and chromatographic separation

Yuezhou Wei, Ruiqin Liu, Yan Wu, Jianhua Zu, Long Zhao, Hitoshi Mimura, Weiqun Shi, Zhifang Chai, Jinling Yang, Youqian Ding

Research output: Contribution to conferencePaperpeer-review

Abstract

To recover U, Pu, MA (Np, Am, Cm) and some specific FPs (Cs, Sr, Tc, etc.) from various spent nuclear fuels (LWR/FBR: Oxide, Metal Fuels), we are studying an advanced hybrid reprocessing system based on UF6 volatilization (Pyro) and chromatographic separation (Aqueous). Spent fuels are decladed by means of thermal and mechanical methods and then applied to the fluorination/volatilization process, which selectively recovers the most amount of U. Then, the remained fuel components are converted to oxides and dissolved by HNO3 solution. Compared to U, since Pu, MA and FPs are significantly less abundant in spent fuels, the scale of the aqueous separation process could become reasonably small and result in less waste. For the chromatographic separation processes, we have prepared different types of porous silica-based organic/inorganic adsorbents with fast diffusion kinetics, improved chemical stability and low pressure drop in a packed column. So they are advantageously applicable to efficient separation of the actinides and FP elements from the fuel dissolved solution. In this work, adsorption and separation behavior of representative actinides and FP elements was studied. Small scale separation tests using simulated and genuine fuel dissolved solutions were carried out to verify the feasibility of the proposed process.

Original languageEnglish
Pages1524-1530
Number of pages7
Publication statusPublished - 2013 Jan 1
EventInternational Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 - Salt Lake City, UT, United States
Duration: 2013 Sept 292013 Oct 3

Other

OtherInternational Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013
Country/TerritoryUnited States
CitySalt Lake City, UT
Period13/9/2913/10/3

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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