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Cronenberg, A.W., Yackle, T.R. (1979) Intergranular fracture of unrestructed UO2 fuel, during film-boiling operation. Journal of Nuclear Materials, 84 (1). 295-318 doi:10.1016/0022-3115(79)90170-3

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Reference TypeJournal (article/letter/editorial)
TitleIntergranular fracture of unrestructed UO2 fuel, during film-boiling operation
JournalJournal of Nuclear Materials
AuthorsCronenberg, A.W.Author
Yackle, T.R.Author
Year1979 (October)Volume84
Issue1
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(79)90170-3Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID4143404Long-form Identifiermindat:1:5:4143404:6
GUID0
Full ReferenceCronenberg, A.W., Yackle, T.R. (1979) Intergranular fracture of unrestructed UO2 fuel, during film-boiling operation. Journal of Nuclear Materials, 84 (1). 295-318 doi:10.1016/0022-3115(79)90170-3
Plain TextCronenberg, A.W., Yackle, T.R. (1979) Intergranular fracture of unrestructed UO2 fuel, during film-boiling operation. Journal of Nuclear Materials, 84 (1). 295-318 doi:10.1016/0022-3115(79)90170-3
In(1979, October) Journal of Nuclear Materials Vol. 84 (1) Elsevier BV

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Cronenberg, A.W., El-Genk, M.S. (1978) An assessment of oxygen diffusion during UO2-zircaloy interaction. Journal of Nuclear Materials, 78 (2). 390-407 doi:10.1016/0022-3115(78)90461-0
Cronenberg, A.W., Fauske, H.K. (1974) UO2 solidification phenomena associated with rapid cooling in liquid sodium. Journal of Nuclear Materials, 52 (1). 24-32 doi:10.1016/0022-3115(74)90022-1
Lippens, M. (1979) Densifications of UO2 β€” PuO2 fuel. Journal of Nuclear Materials, 81 (1). 99-105 doi:10.1016/0022-3115(79)90068-0
Radford, K.C. (1979) Effect of fabrication parameters and microstructure on the mechanical strength of UO2 fuel pellets. Journal of Nuclear Materials, 84 (1). 222-236 doi:10.1016/0022-3115(79)90165-x
Greatley, C.J., Hargreaves, R. (1979) The measured emission of fission-product gases from operating uo2 fuel. Journal of Nuclear Materials, 79 (1). 235-245 doi:10.1016/0022-3115(79)90451-3
Tucker, M.O. (1979) The growth of grain edge porosity in irradiated UO2. Journal of Nuclear Materials, 79 (1). 206-213 doi:10.1016/0022-3115(79)90448-3
Armstrong, T.R. (1979) The onset of radiation-blistering in low-temperature D+-irradiated copper. Journal of Nuclear Materials, 84 (1). 118-124 doi:10.1016/0022-3115(79)90155-7
Tucker, M.O., White, R.J. (1979) The release of unstable fission products from UO2 during irradiation. Journal of Nuclear Materials, 87 (1). 1-10 doi:10.1016/0022-3115(79)90121-1
Klepfer, H.H. (1963) Zirconium-niobium binary alloys for boiling water reactor service part II - corrosion hydrogen embrittlement. Journal of Nuclear Materials, 9 (1). 77-84 doi:10.1016/0022-3115(63)90170-3
(1979) Subject index. Journal of Nuclear Materials, 81 (1). 295-296 doi:10.1016/0022-3115(79)90092-8
Rest, J., Cronenberg, A.W. (1987) Modeling the behavior of Xe, I, Cs, Te, Ba, and Sr in solid and liquefied fuel during severe accidents. Journal of Nuclear Materials, 150 (2). 203-225 doi:10.1016/0022-3115(87)90076-6
 
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