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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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Reference TypeJournal (article/letter/editorial)
TitleMelting temperature and thermal conductivity of irradiated mixed oxide fuel
JournalJournal of Nuclear Materials
AuthorsYamamoto, K.Author
Hirosawa, T.Author
Yoshikawa, K.Author
Morozumi, K.Author
Nomura, S.Author
Year1993 (September)Volume204
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(93)90203-bSearch in ResearchGate
Generate Citation Formats
Mindat Ref. ID4150648Long-form Identifiermindat:1:5:4150648:6
GUID0
Full ReferenceYamamoto, 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
Plain TextYamamoto, 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
In(1993) Journal of Nuclear Materials Vol. 204. Elsevier BV

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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
Tsai, H., Neimark, L.A., Asaga, T., Shikakura, S. (1993) Behavior of mixed-oxide fuel elements during an overpower transient. Journal of Nuclear Materials, 204. 217-227 doi:10.1016/0022-3115(93)90220-s
Ukai, S., Harada, M., Okada, H., Inoue, M., Nomura, S., Shikakura, S., Nishida, T., Fujiwara, M., Asabe, K. (1993) Tube manufacturing and mechanical properties of oxide dispersion strengthened ferritic steel. Journal of Nuclear Materials, 204. 74-80 doi:10.1016/0022-3115(93)90201-9
Ukai, S., Harada, M., Okada, H., Inoue, M., Nomura, S., Shikakura, S., Asabe, K., Nishida, T., Fujiwara, M. (1993) Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials. Journal of Nuclear Materials, 204. 65-73 doi:10.1016/0022-3115(93)90200-i
Philipponneau, Y. (1992) Thermal conductivity of (U, Pu)O2βˆ’x mixed oxide fuel. Journal of Nuclear Materials, 188. 194-197 doi:10.1016/0022-3115(92)90470-6
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
Strain, R.V., Bottcher, J.H., Ukai, S., Arii, Y. (1993) Fuel-sodium reaction product and its influence on breached mixed-oxide fuel pins. Journal of Nuclear Materials, 204. 252-260 doi:10.1016/0022-3115(93)90224-m
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
Venetch, J., Johnson, A.A., Mukherjee, K. (1970) Thermal hardening in neutron irradiated vanadium. Journal of Nuclear Materials, 34 (3). 343-344 doi:10.1016/0022-3115(70)90203-5
Herbig, R., Rudolph, K., Lindau, B., Skiba, O.V., Maershin, A.A. (1993) Vibrocompacted fuel for the liquid metal reactor BOR-60. Journal of Nuclear Materials, 204. 93-101 doi:10.1016/0022-3115(93)90204-c
Ogawa, T., Ikawa, K. (1981) High-temperature heating experiments on unirradiated ZrC-coated fuel particles. Journal of Nuclear Materials, 99 (1). 85-93 doi:10.1016/0022-3115(81)90141-0
 
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