R&D progress on recovery/recycle of zirconium from used fuel cladding

Emory D. Collins; Guillermo Daniel DelCul; Barry B. Spencer; Jared A. Johnson; Ronald R. Brunson; Rodney D. Hunt

R&D progress on recovery/recycle of zirconium from used fuel cladding

Emory D. Collins, Guillermo Daniel DelCul, Barry B. Spencer, Jared A. Johnson, Ronald R. Brunson, Rodney D. Hunt

Research output: Contribution to journal › Article › peer-review

Abstract

A dry chlorination process for the recovery and purification of zirconium from used nuclear fuel (UNF) cladding is being developed at ORNL. Feasibility tests with actual UNF have demonstrated that impurities can be removed from UNF cladding in a process that produces recovered zirconium that can be handled with¬out shielding or significant dose. Glassware equipment has been used for all preliminary tests of the process, including those made to scale up the process from approximately 15 g/batch to 500 g/batch, the latter producing more than 1 kilogram of zirconium salt per batch.

Original language	English
Pages (from-to)	52-54
Number of pages	3
Journal	Radwaste Solutions
Volume	23
Issue number	1
State	Published - Mar 1 2016

Cite this

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title = "R&D progress on recovery/recycle of zirconium from used fuel cladding",

abstract = "A dry chlorination process for the recovery and purification of zirconium from used nuclear fuel (UNF) cladding is being developed at ORNL. Feasibility tests with actual UNF have demonstrated that impurities can be removed from UNF cladding in a process that produces recovered zirconium that can be handled with¬out shielding or significant dose. Glassware equipment has been used for all preliminary tests of the process, including those made to scale up the process from approximately 15 g/batch to 500 g/batch, the latter producing more than 1 kilogram of zirconium salt per batch.",

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AU - Collins, Emory D.

AU - DelCul, Guillermo Daniel

AU - Spencer, Barry B.

AU - Johnson, Jared A.

AU - Brunson, Ronald R.

AU - Hunt, Rodney D.

PY - 2016/3/1

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N2 - A dry chlorination process for the recovery and purification of zirconium from used nuclear fuel (UNF) cladding is being developed at ORNL. Feasibility tests with actual UNF have demonstrated that impurities can be removed from UNF cladding in a process that produces recovered zirconium that can be handled with¬out shielding or significant dose. Glassware equipment has been used for all preliminary tests of the process, including those made to scale up the process from approximately 15 g/batch to 500 g/batch, the latter producing more than 1 kilogram of zirconium salt per batch.

AB - A dry chlorination process for the recovery and purification of zirconium from used nuclear fuel (UNF) cladding is being developed at ORNL. Feasibility tests with actual UNF have demonstrated that impurities can be removed from UNF cladding in a process that produces recovered zirconium that can be handled with¬out shielding or significant dose. Glassware equipment has been used for all preliminary tests of the process, including those made to scale up the process from approximately 15 g/batch to 500 g/batch, the latter producing more than 1 kilogram of zirconium salt per batch.

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JO - Radwaste Solutions

JF - Radwaste Solutions

IS - 1

ER -

R&D progress on recovery/recycle of zirconium from used fuel cladding

Abstract

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