R&D Progress on Recovery/Recycle of Zirconium from Used Fuel Cladding

Journal Article · Fri Apr 01 00:00:00 EDT 2016 · Radwaste Solutions

OSTI ID:1362199

Collins, Emory D. ^[1]; DelCul, Guillermo Daniel ^[1]; Brunson, Ronald Ray ^[1]; Johnson, Jared A. ^[1]; Spencer, Barry B. ^[1]; Hunt, Rodney Dale ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

There has been significant progress accomplished at Oak Ridge National Laboratory (ORNL) on the development of a dry chlorination process for recovery and purification of zirconium from used nuclear fuel (UNF) cladding by conversion to zirconium tetrachloride, which sublimes to a vapor and is then condensed as a dry salt product, essentially free of fuel and alloy components (impurities). We have accomplished significant progress on developing a chlorination process for removing the zirconium in UNF cladding and purifying the product salt for re-use—possibly in manufacture of new cladding, or at a minimum to meet specifications for disposal as low level waste.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1362199
• Journal Information: Radwaste Solutions, Vol. 23, Issue 1; ISSN 1529-4900
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS