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

Abstract

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.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1362199
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article
Journal Name:
Radwaste Solutions
Additional Journal Information:
Journal Volume: 23; Journal Issue: 1; Journal ID: ISSN 1529-4900
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Collins, Emory D., DelCul, Guillermo Daniel, Brunson, Ronald Ray, Johnson, Jared A., Spencer, Barry B., and Hunt, Rodney Dale. R&D Progress on Recovery/Recycle of Zirconium from Used Fuel Cladding. United States: N. p., 2016. Web.
Collins, Emory D., DelCul, Guillermo Daniel, Brunson, Ronald Ray, Johnson, Jared A., Spencer, Barry B., & Hunt, Rodney Dale. R&D Progress on Recovery/Recycle of Zirconium from Used Fuel Cladding. United States.
Collins, Emory D., DelCul, Guillermo Daniel, Brunson, Ronald Ray, Johnson, Jared A., Spencer, Barry B., and Hunt, Rodney Dale. Fri . "R&D Progress on Recovery/Recycle of Zirconium from Used Fuel Cladding". United States.
@article{osti_1362199,
title = {R&D Progress on Recovery/Recycle of Zirconium from Used Fuel Cladding},
author = {Collins, Emory D. and DelCul, Guillermo Daniel and Brunson, Ronald Ray and Johnson, Jared A. and Spencer, Barry B. and Hunt, Rodney Dale},
abstractNote = {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.},
doi = {},
journal = {Radwaste Solutions},
issn = {1529-4900},
number = 1,
volume = 23,
place = {United States},
year = {2016},
month = {4}
}