The effect of re-solution models on fission gas disposition in irradiated UO2 fuel
作者： A. R. Wazzan , A. Villalobos , D. Okrent
DOI: 10.13182/NT85-A33654
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摘要: … swelling is more important than grain-face bubble swelling, but is about one order of magnitude smaller than grain-edge bubble swelling … at.%, grain-edge bubble swelling is not only the …
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sci-hub.se 参考文章(12)
Antonio Villalobos, A. R. Wazzan, D. Okrent, Analysis of Fission Gas Disposition in Light Water Reactor Steady-State Operation Nuclear Technology. ,vol. 58, pp. 492- 510 ,(1982) , 10.13182/NT82-A32983
M. V. Speight, A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation Nuclear Science and Engineering. ,vol. 37, pp. 180- 185 ,(1969) , 10.13182/NSE69-A20676
William L. Baldewicz, Ahmed R. Wazzan, David Okrent, Modeling of Equiaxed Grain Growth in Uranium Dioxide Fuels Nuclear Technology. ,vol. 46, pp. 263- 267 ,(1979) , 10.13182/NT79-A32326
J.B. Ainscough, B.W. Oldfield, J.O. Ware, Isothermal grain growth kinetics in sintered UO2 pellets Journal of Nuclear Materials. ,vol. 49, pp. 117- 128 ,(1973) , 10.1016/0022-3115(73)90001-9
M. V. Speight, G. W. Greenwood, Grain boundary mobility and its effects in materials containing inert gases Philosophical Magazine. ,vol. 9, pp. 683- 689 ,(1964) , 10.1080/14786436408211880
R.S. Nelson, The stability of gas bubbles in an irradiation environment Journal of Nuclear Materials. ,vol. 31, pp. 153- 161 ,(1969) , 10.1016/0022-3115(69)90189-5
M.H. Wood, J.R. Matthews, A simple operational gas release and swelling model Journal of Nuclear Materials. ,vol. 91, pp. 35- 40 ,(1980) , 10.1016/0022-3115(80)90029-X
W.G. Steele, A.R. Wazzan, D. Okrent, Fission gas disposition in decay heat environment Nuclear Engineering and Design. ,vol. 70, pp. 187- 199 ,(1982) , 10.1016/0029-5493(82)90198-4
C. Ronchi, I.L.F. Ray, H. Thiele, J. van de Laar, Swelling analysis of highly-rated MX-type LMFBR fuels: II. Microsopic swelling behaviour Journal of Nuclear Materials. ,vol. 74, pp. 193- 211 ,(1978) , 10.1016/0022-3115(78)90359-8
D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements ,(1976)