Dry pretreatment of used nuclear fuel to simplify storage or recycling-zirconium recycling from cladding

E. D. Collins; G. D. DelCul; B. B. Spencer; R. T. Jubin; R. R. Brunson; J. A. Johnson

Dry pretreatment of used nuclear fuel to simplify storage or recycling-zirconium recycling from cladding

E. D. Collins, G. D. DelCul, B. B. Spencer, R. T. Jubin, R. R. Brunson, J. A. Johnson

Research output: Contribution to journal › Conference article › peer-review

1 Scopus citations

Abstract

Based on the results of process studies described, and with the assistance of the industrial teams with equipment design, process design and scale-up optimization tests are continuing to evaluate the chlorination process using dry Cl₂ as the reagent. The objective is to produce a recycled zirconium product that can be reused for nuclear fuel cladding manufacture.

Original language	English
Pages (from-to)	246
Number of pages	1
Journal	Transactions of the American Nuclear Society
Volume	107
State	Published - 2012
Event	2012 ANS Annual Winter Meeting - San Diego, CA, United States Duration: Nov 11 2012 → Nov 15 2012

Cite this

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title = "Dry pretreatment of used nuclear fuel to simplify storage or recycling-zirconium recycling from cladding",

abstract = "Based on the results of process studies described, and with the assistance of the industrial teams with equipment design, process design and scale-up optimization tests are continuing to evaluate the chlorination process using dry Cl2 as the reagent. The objective is to produce a recycled zirconium product that can be reused for nuclear fuel cladding manufacture.",

author = "Collins, \{E. D.\} and DelCul, \{G. D.\} and Spencer, \{B. B.\} and Jubin, \{R. T.\} and Brunson, \{R. R.\} and Johnson, \{J. A.\}",

year = "2012",

language = "English",

volume = "107",

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journal = "Transactions of the American Nuclear Society",

issn = "0003-018X",

note = "2012 ANS Annual Winter Meeting ; Conference date: 11-11-2012 Through 15-11-2012",

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TY - JOUR

T1 - Dry pretreatment of used nuclear fuel to simplify storage or recycling-zirconium recycling from cladding

AU - Collins, E. D.

AU - DelCul, G. D.

AU - Spencer, B. B.

AU - Jubin, R. T.

AU - Brunson, R. R.

AU - Johnson, J. A.

PY - 2012

Y1 - 2012

N2 - Based on the results of process studies described, and with the assistance of the industrial teams with equipment design, process design and scale-up optimization tests are continuing to evaluate the chlorination process using dry Cl2 as the reagent. The objective is to produce a recycled zirconium product that can be reused for nuclear fuel cladding manufacture.

AB - Based on the results of process studies described, and with the assistance of the industrial teams with equipment design, process design and scale-up optimization tests are continuing to evaluate the chlorination process using dry Cl2 as the reagent. The objective is to produce a recycled zirconium product that can be reused for nuclear fuel cladding manufacture.

UR - https://www.scopus.com/pages/publications/84876521974

M3 - Conference article

AN - SCOPUS:84876521974

SN - 0003-018X

VL - 107

SP - 246

JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

T2 - 2012 ANS Annual Winter Meeting

Y2 - 11 November 2012 through 15 November 2012

ER -

Dry pretreatment of used nuclear fuel to simplify storage or recycling-zirconium recycling from cladding

Abstract

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