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Plitz, H., Crittenden, G.C., Languille, A. (1993) Experience with failed LMR oxide fuel element performance in European fast reactors. Journal of Nuclear Materials, 204. 238-243 doi:10.1016/0022-3115(93)90222-k

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Reference TypeJournal (article/letter/editorial)
TitleExperience with failed LMR oxide fuel element performance in European fast reactors
JournalJournal of Nuclear Materials
AuthorsPlitz, H.Author
Crittenden, G.C.Author
Languille, A.Author
Year1993 (September)Volume204
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(93)90222-kSearch in ResearchGate
Generate Citation Formats
Mindat Ref. ID4150667Long-form Identifiermindat:1:5:4150667:1
GUID0
Full ReferencePlitz, H., Crittenden, G.C., Languille, A. (1993) Experience with failed LMR oxide fuel element performance in European fast reactors. Journal of Nuclear Materials, 204. 238-243 doi:10.1016/0022-3115(93)90222-k
Plain TextPlitz, H., Crittenden, G.C., Languille, A. (1993) Experience with failed LMR oxide fuel element performance in European fast reactors. Journal of Nuclear Materials, 204. 238-243 doi:10.1016/0022-3115(93)90222-k
In(1993) Journal of Nuclear Materials Vol. 204. Elsevier BV

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Brown, C., Languille, A., Muehling, G. (1993) Status of LMR fuel development in Europe. Journal of Nuclear Materials, 204. 33-38 doi:10.1016/0022-3115(93)90196-6
Kittel, J.H, Frost, B.R.T, Mustelier, J.P, Bagley, K.Q, Crittenden, G.C, Van Dievoet, J (1993) History of fast reactor fuel development. Journal of Nuclear Materials, 204. 1-13 doi:10.1016/0022-3115(93)90193-3
Ford, I.J., Mignanelli, M.A. (1993) The development of the enpanne code to model failed fast reactor fuel pins. Journal of Nuclear Materials, 204. 180-187 doi:10.1016/0022-3115(93)90215-k
Melis, J.-C., Plitz, H., Thetford, R. (1993) Highly irradiated fuel behaviour up to melting: JOG tests in CABRI. Journal of Nuclear Materials, 204. 212-216 doi:10.1016/0022-3115(93)90219-o
Leggett, R.D., Walters, L.C. (1993) Status of LMR fuel development in the United States of America. Journal of Nuclear Materials, 204. 23-32 doi:10.1016/0022-3115(93)90195-5
Williams, J. (1972) Fuel element experience in nuclear power reactors; an AEG monograph. Journal of Nuclear Materials, 43 (3). 354pp. doi:10.1016/0022-3115(72)90071-2
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Katsuragawa, M., Kashihara, H., Akebi, M. (1993) Status of liquid metal fast breeder reactor fuel development in Japan. Journal of Nuclear Materials, 204. 14-22 doi:10.1016/0022-3115(93)90194-4
Boltax, A., Garkisch, H.D., Hirai, K., Mitsugi, T. (1993) Irradiation behavior of advanced mixed-oxide fuel pins in EBR-II. Journal of Nuclear Materials, 204. 148-156 doi:10.1016/0022-3115(93)90211-g
Crawford, D.C., Lahm, C.E., Tsai, H., Pahl, R.G. (1993) Performance of U-Pu-Zr fuel cast into zirconium molds. Journal of Nuclear Materials, 204. 157-164 doi:10.1016/0022-3115(93)90212-h
Yamamoto, K., Hirosawa, T., Yoshikawa, K., Morozumi, K., Nomura, S. (1993) Melting temperature and thermal conductivity of irradiated mixed oxide fuel. Journal of Nuclear Materials, 204. 85-92 doi:10.1016/0022-3115(93)90203-b
 
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