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Mogensen, M., Bagger, C., Toftegaard, H., Knudsen, P., Walker, C.T. (1993) Observations of athermal gas release from water-reactor fuel at extended burnup. Journal of Nuclear Materials, 202 (3). 199-209 doi:10.1016/0022-3115(93)90388-f

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Reference TypeJournal (article/letter/editorial)
TitleObservations of athermal gas release from water-reactor fuel at extended burnup
JournalJournal of Nuclear Materials
AuthorsMogensen, M.Author
Bagger, C.Author
Toftegaard, H.Author
Knudsen, P.Author
Walker, C.T.Author
Year1993 (July)Volume202
Issue3
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(93)90388-fSearch in ResearchGate
Generate Citation Formats
Mindat Ref. ID4150579Long-form Identifiermindat:1:5:4150579:7
GUID0
Full ReferenceMogensen, M., Bagger, C., Toftegaard, H., Knudsen, P., Walker, C.T. (1993) Observations of athermal gas release from water-reactor fuel at extended burnup. Journal of Nuclear Materials, 202 (3). 199-209 doi:10.1016/0022-3115(93)90388-f
Plain TextMogensen, M., Bagger, C., Toftegaard, H., Knudsen, P., Walker, C.T. (1993) Observations of athermal gas release from water-reactor fuel at extended burnup. Journal of Nuclear Materials, 202 (3). 199-209 doi:10.1016/0022-3115(93)90388-f
In(1993, July) Journal of Nuclear Materials Vol. 202 (3) Elsevier BV

See Also

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Bagger, C., Mogensen, M., Walker, C.T. (1994) Temperature measurements in high burnup UO2 nuclear fuel: Implications for thermal conductivity, grain growth and gas release. Journal of Nuclear Materials, 211 (1). 11-29 doi:10.1016/0022-3115(94)90276-3
Mogensen, M., Bagger, C., Walker, C.T. (1993) An experimental study of the distribution of retained xenon in transient-tested UO2 fuel. Journal of Nuclear Materials, 199 (2). 85-101 doi:10.1016/0022-3115(93)90285-7
Walker, C.T., Bagger, C., Mogensen, M. (1996) Observations on the release of cesium from UO2 fuel. Journal of Nuclear Materials, 240 (1). 32-42 doi:10.1016/s0022-3115(96)00477-1
Walker, C.T., Mogensen, M. (1987) On the rate determining step in fission gas release from high burn-up water reactor fuel during power transients. Journal of Nuclear Materials, 149 (2). 121-131 doi:10.1016/0022-3115(87)90469-7
Mogensen, M., Walker, C.T., Ray, I.L.F., Coquerelle, M. (1985) Local fission gas release and swelling in water reactor fuel during slow power transients. Journal of Nuclear Materials, 131 (2). 162-171 doi:10.1016/0022-3115(85)90455-6
Walker, C.T., Bagger, C., Mogensen, M. (1990) Migration of fission product barium in UO2 fuel under transient conditions. Journal of Nuclear Materials, 173 (1). 14-25 doi:10.1016/0022-3115(90)90308-a
Walker, C.T., Knappik, P., Mogensen, M. (1988) Concerning the development of grain face bubbles and fission gas release in UO2 fuel. Journal of Nuclear Materials, 160 (1). 10-23 doi:10.1016/0022-3115(88)90003-7
Cunningham, M.E., Freshley, M.D., Lanning, D.D. (1993) Fission gas release during power bumping at high burnup. Journal of Nuclear Materials, 200 (1). 24-40 doi:10.1016/0022-3115(93)90006-k
Walker, C.T., Goll, W., Matsumura, T. (1996) Effect of inhomogeneity on the level of fission gas and caesium release from OCOM MOX fuel during irradiation. Journal of Nuclear Materials, 228 (1). 8-17 doi:10.1016/0022-3115(95)00191-3
Lassmann, K., Walker, C.T., van de Laar, J., Lindström, F. (1995) Modelling the high burnup UO2 structure in LWR fuel. Journal of Nuclear Materials, 226 (1). 1-8 doi:10.1016/0022-3115(95)00116-6
Lassmann, K., Walker, C.T., van de Laar, J. (1998) Extension of the TRANSURANUS burnup model to heavy water reactor conditions. Journal of Nuclear Materials, 255 (2). 222-233 doi:10.1016/s0022-3115(98)00019-1
 
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