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Smith, H.D, Baldwin, D.L (1993) An investigation of thermal release of carbon-14 from PWR Zircaloy spent fuel cladding. Journal of Nuclear Materials, 200 (1). 128-137 doi:10.1016/0022-3115(93)90016-r

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Reference TypeJournal (article/letter/editorial)
TitleAn investigation of thermal release of carbon-14 from PWR Zircaloy spent fuel cladding
JournalJournal of Nuclear Materials
AuthorsSmith, H.DAuthor
Baldwin, D.LAuthor
Year1993 (March)Volume200
Issue1
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(93)90016-rSearch in ResearchGate
Generate Citation Formats
Mindat Ref. ID4150459Long-form Identifiermindat:1:5:4150459:4
GUID0
Full ReferenceSmith, H.D, Baldwin, D.L (1993) An investigation of thermal release of carbon-14 from PWR Zircaloy spent fuel cladding. Journal of Nuclear Materials, 200 (1). 128-137 doi:10.1016/0022-3115(93)90016-r
Plain TextSmith, H.D, Baldwin, D.L (1993) An investigation of thermal release of carbon-14 from PWR Zircaloy spent fuel cladding. Journal of Nuclear Materials, 200 (1). 128-137 doi:10.1016/0022-3115(93)90016-r
In(1993, March) Journal of Nuclear Materials Vol. 200 (1) Elsevier BV

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Papp, Reiner (1993) Guidebook on Spent Fuel Storage. Journal of Nuclear Materials, 200 (2). 270pp. doi:10.1016/0022-3115(93)90338-y
Franklin, D.G., Fisher, H.D. (1977) Requirements for in-reactor Zircaloy creep measurements for application in the design of PWR fuel. Journal of Nuclear Materials, 65. 192-199 doi:10.1016/0022-3115(77)90055-1
Kopp, D., Münzel, H. (1990) Release of volatile carbon-14 containing products from Zircaloy. Journal of Nuclear Materials, 173 (1). 1-6 doi:10.1016/0022-3115(90)90306-8
Rudisill, Tracy S. (2009) Decontamination of Zircaloy cladding hulls from spent nuclear fuel. Journal of Nuclear Materials, 385 (1). 193-195 doi:10.1016/j.jnucmat.2008.10.016
Wadman, Boel, Andrén, Hans-Olof, Nyström, Anna-Lena, Rudling, Peter, Pettersson, Håkan (1993) Microstructural influence on uniform corrosion of Zircaloy nuclear fuel claddings. Journal of Nuclear Materials, 200 (2). 207-217 doi:10.1016/0022-3115(93)90331-r
Jung, Y.H., Baik, S.J., Ahn, S.B. (2019) Investigation of Zircaloy-fuel interaction in failed spent PWR fuel using EPMA. Journal of Nuclear Materials, 517. 349-355 doi:10.1016/j.jnucmat.2019.02.025
Gebhardt, Olaf (1993) Investigation of in-pile formed corrosion films on Zircaloy fuel rod claddings by impedance spectroscopy and galvanostatic anodization. Journal of Nuclear Materials, 203 (1). 17-26 doi:10.1016/0022-3115(93)90425-x
Hood, G.M., Schultz, R.J. (1993) Chromium diffusion in α-zirconium, Zircaloy-2 and Zr-2.5Nb. Journal of Nuclear Materials, 200 (1). 141-143 doi:10.1016/0022-3115(93)90018-t
(1993) Editorial Board. Journal of Nuclear Materials, 200 (1). doi:10.1016/0022-3115(93)90001-f
Kutty, T.R.G., Ganguly, C. (1993) Identation creep of Zircaloy-2 welds of nuclear fuel pins. Journal of Nuclear Materials, 207. 345-349 doi:10.1016/0022-3115(93)90279-8
Baldwin, D.L., Slagle, O.D., Gelles, D.S. (1991) Tritium release from irradiated beryllium at elevated temperatures. Journal of Nuclear Materials, 179. 329-334 doi:10.1016/0022-3115(91)90093-m
 
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