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 language | English |
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Pages | 1524-1530 |
Number of pages | 7 |
Publication status | Published - 2013 Jan 1 |
Event | International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 - Salt Lake City, UT, United States Duration: 2013 Sept 29 → 2013 Oct 3 |
Other
Other | International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 |
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Country/Territory | United States |
City | Salt Lake City, UT |
Period | 13/9/29 → 13/10/3 |
ASJC Scopus subject areas
- Energy Engineering and Power Technology
- Nuclear Energy and Engineering