Design, fabrication, and testing of a laboratory-scale voloxidation system for removal of tritium and other volatile fission products from used nuclear fuel

B. B. Spencer; G. D. Del Cul; E. C. Bradley; R. T. Jubin; T. D. Hylton; E. D. Collins

Design, fabrication, and testing of a laboratory-scale voloxidation system for removal of tritium and other volatile fission products from used nuclear fuel

B. B. Spencer, G. D. Del Cul, E. C. Bradley, R. T. Jubin, T. D. Hylton, E. D. Collins

Process Coordination

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

1 Scopus citations

Original language	English
Pages (from-to)	103-104
Number of pages	2
Journal	Transactions of the American Nuclear Society
Volume	98
State	Published - 2008
Event	2008 Annual Meeting on American Nuclear Society - Anaheim, CA, United States Duration: Jun 8 2008 → Jun 12 2008

Cite this

@article{1686c2426f6c491f951c926ef32855e3,

title = "Design, fabrication, and testing of a laboratory-scale voloxidation system for removal of tritium and other volatile fission products from used nuclear fuel",

author = "Spencer, {B. B.} and {Del Cul}, {G. D.} and Bradley, {E. C.} and Jubin, {R. T.} and Hylton, {T. D.} and Collins, {E. D.}",

year = "2008",

language = "English",

volume = "98",

pages = "103--104",

journal = "Transactions of the American Nuclear Society",

issn = "0003-018X",

note = "2008 Annual Meeting on American Nuclear Society ; Conference date: 08-06-2008 Through 12-06-2008",

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TY - JOUR

T1 - Design, fabrication, and testing of a laboratory-scale voloxidation system for removal of tritium and other volatile fission products from used nuclear fuel

AU - Spencer, B. B.

AU - Del Cul, G. D.

AU - Bradley, E. C.

AU - Jubin, R. T.

AU - Hylton, T. D.

AU - Collins, E. D.

PY - 2008

Y1 - 2008

UR - http://www.scopus.com/inward/record.url?scp=55249104726&partnerID=8YFLogxK

M3 - Conference article

AN - SCOPUS:55249104726

SN - 0003-018X

VL - 98

SP - 103

EP - 104

JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

T2 - 2008 Annual Meeting on American Nuclear Society

Y2 - 8 June 2008 through 12 June 2008

ER -

Design, fabrication, and testing of a laboratory-scale voloxidation system for removal of tritium and other volatile fission products from used nuclear fuel

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