참고문헌
-
P.G. Lucuta, R.A. Verrall, Hj. Matzke and B.J. Palmer, "Microstructural Features of SIMFUEL - Simulated Highburnup
$UO_2$ Based Nuclear Fuel", Journal of Nuclear Materials, Vol. 178, p.48 (1991) https://doi.org/10.1016/0022-3115(91)90455-G - H. Kleycamp, "The Chemical State of the Fission Products in Oxide Fuels", Journal of Nuclear Materials, Vol. 131, p.221 (1985) https://doi.org/10.1016/0022-3115(85)90460-X
-
Philippe Martin, Michel Ripert, Gaelle Carlot, Philippe Parent and Carine Laffon, "A Study of Molybdenum Behaviour in
$UO_2$ by X-ray Absorption Spectroscopy", Journal of Nuclear Materials, Vol.326, p.132 (2004) https://doi.org/10.1016/j.jnucmat.2004.01.006 - P. Garcia, J.P. Piron and D. Baron, "A Model for the Oxygen Potential of Oxide Fuels at High Burnup", in "Proceedings of Water Reactor Fuel Element Modeling at High Burnup and its Experimental Support", IAEA-TECDOC-957, p. 523-538 (1997)
- I. Sato, H. Furuya, T. Arima, K. Idemitsu and K. Yamamoto, "Behavior of Metallic Fission Products in Uranium-Plutonium Mixed Oxide Fuel", Journal of Nuclear Materials, Vol.273, p.239 (1999) https://doi.org/10.1016/S0022-3115(99)00071-9
- S. Nicoll, H. Matzke, R.W. Grimes, C.R.A. Catlow, "The Behavior of Single Atoms of Molybdenum in Uranis", Journal of Nuclear Materials, Vol.240, p.185 (1997) https://doi.org/10.1016/S0022-3115(96)00716-7
- E. Walle, P. Perrot, J. Foct, and M. Parise, "Evaluation of the Cs-Mo-I-O and Cs-U-I-O Diagrams and Determination of Iodine and Oxygen Partial Pressure in Spent Nuclear Fuel Rods", Journal of Physics and Chemistry of Solids, Vol. 66, p.655 (2005) https://doi.org/10.1016/j.jpcs.2004.06.078
- Y.-K. Ha, J. Kim, Y.S. Jeon, S.H. Han, H.S. Seo and K. Song, "Local Burnup Characteristics of PWR Spent Nuclear Fuels Discharged from Yeonggwang-2 Nuclear Power Plant", Nuclear Engineering and Technology, Vol. 42(1), p.79 (2010) https://doi.org/10.5516/NET.2010.42.1.079
-
Hj. Matzke, "On the rim effect in high burnup
$UO_2$ LWR fuels", Journal of Nuclear Materials, Vol. 189, 141-148, (1992) https://doi.org/10.1016/0022-3115(92)90428-N -
H. Kleykamp, "Solubility of Selected Fission Products in
$UO_2$ and (U,Pu)$O_2$ ", Journal of Nuclear Materials, Vol.206, p.82 (1993) https://doi.org/10.1016/0022-3115(93)90236-R - R.D. Shannon, "Revised Effective Ionic Radii and Systematic Studies of Interatomic Distances in Halides and Chalcogenides", Acta Crystallographica, A 32, p.751, (1976) https://doi.org/10.1107/S0567739476001551
- A.R. West, "Basic Solid State Chemistry", JOHN WILLEY & SONS, p.253 (1991)
- N-J. Cobos, D. Papaioannou, J. Spino and M. Coquerelle, "Phase Characterization of Simulated High Burnup UO2 Fuel", J. Alloys and Compounds, Vol. 271-273, p.610 (1998) https://doi.org/10.1016/S0925-8388(98)00170-4
-
Y.-K. Ha, J.-G. Kim, Y.-J. Park and W.-H. Kim, "Studies on the Air-Oxidation Behavior of Uranium Dioxide; I. Phase Transformation from
$(U_{1-y}Gd_y)O_2$ to$(U_{1-y}Gd_y)_3O_8$ ", Journal of Nuclear Science and Technology, Vol. supp. 3, p.772 (2002) -
S. Imoto, "Chemical state of fission Products in irradiated
$UO_2$ ", Journal of Nuclear Materials, Vol. 140(1), p.19 (1986) https://doi.org/10.1016/0022-3115(86)90192-3 - T. Muromura, T. Adachi, H. Takeishi, Z. Yoshida, T. Yamamoto, K. Ueno, "Metallic Phases Precipitated in UO2 Fuel: I. Phases in Simulated Fuel", Journal of Nuclear Materials, Vol. 151, p.318 (1988) https://doi.org/10.1016/0022-3115(88)90026-8
- T. Adachi, T. Muromura, H. Takeishi and T. Yamamoto, "Metallic Phases Precipitated in UO2 Fuel: II. Insoluble residue in Simulated Fuel", Journal of Nuclear Materials, Vol. 160, p.81 (1988) https://doi.org/10.1016/0022-3115(88)90011-6
피인용 문헌
- Specific Features of the Crystal Chemistry of Layered Uranyl Compounds with the Ratio UO2: TO4 = 5 : 8 (T = S6+, Cr6+, Se6+, Mo6+) vol.60, pp.4, 2018, https://doi.org/10.1134/S1066362218040033