@inproceedings{41f5a3b4838f485183de727a2e871ab0,
title = "Chlorination process development for zirconium recovery from used fuel cladding",
abstract = "Development of a process for recovery and recycle of zirconium from used nuclear fuel (UNF) cladding was continued in 2014. New studies were done with nonradioactive cladding to determine (1) the quantitative effects of an anhydrous oxide coating layer on the subsequent chlorination reaction, (2) the effects of varying chlorination process parameters, and (3) scaling up the amount of cladding from 15 to 500 g. The larger amount produced greater than 1 kg of ZrCl4 salt product.",
author = "Collins, {Emory D.} and {Del Cul}, {G. D.} and Spencer, {B. B.} and Hunt, {R. D.} and Brunson, {R. R.} and C. Ausmus",
year = "2015",
language = "English",
series = "15th International High-Level Radioactive Waste Management Conference 2015, IHLRWM 2015",
publisher = "American Nuclear Society",
pages = "165b--168",
booktitle = "15th International High-Level Radioactive Waste Management Conference 2015, IHLRWM 2015",
note = "15th International High-Level Radioactive Waste Management Conference, IHLRWM 2015 ; Conference date: 12-04-2015 Through 16-04-2015",
}