Browse > Article
http://dx.doi.org/10.5516/NET.2011.43.3.309

BEHAVIORS OF MOLYBDENUM IN UO2 FUEL MATRIX  

Ha, Yeong-Keong (Korea Atomic Energy Research Institute)
Kim, Jong-Goo (Korea Atomic Energy Research Institute)
Park, Yang-Soon (Korea Atomic Energy Research Institute)
Park, Soon-Dal (Korea Atomic Energy Research Institute)
Song, Kyu-Seok (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.43, no.3, 2011 , pp. 309-316 More about this Journal
Abstract
Molybdenum is the most abundant fission product since its fission yield is equivalent to that of xenon, and it has a very special role in the chemistry of nuclear fuel because it influences the oxygen potential of $UO_2$ fuel. In this study, the distribution of molybdenum in spent $UO_2$ fuel specimens with 33.3, 41.0 and 57.6 GWd/tU burnup was measured by a LA-ICP-MS system and the reproducibility of the measured data was obtained. The Mo distribution was almost constant along the radius of a fuel except an increase at the periphery of the fuel. It showed a drop in reproducibility with relatively high deviation of measured values for the highest burnup fuel. To explain this, the state of molybdenum in a $UO_2$ matrix and its effect on the oxidation behavior of $UO_2$ were investigated. The low reproducibility was explained by the segregation of molybdenum, and the inhibition of oxidation by the molybdenum was also observed.
Keywords
Molybdenum; Uranium Dioxide; Distribution; Chemical State; Oxidation;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
Times Cited By Web Of Science : 0  (Related Records In Web of Science)
Times Cited By SCOPUS : 0
연도 인용수 순위
1 A.R. West, "Basic Solid State Chemistry", JOHN WILLEY & SONS, p.253 (1991)
2 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)   DOI
3 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)
4 S. Imoto, "Chemical state of fission Products in irradiated $UO_2$", Journal of Nuclear Materials, Vol. 140(1), p.19 (1986)   DOI
5 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)   DOI
6 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)   DOI
7 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)   DOI
8 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)
9 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)   DOI
10 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)   DOI
11 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)   DOI
12 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)   DOI
13 H. Kleycamp, "The Chemical State of the Fission Products in Oxide Fuels", Journal of Nuclear Materials, Vol. 131, p.221 (1985)   DOI   ScienceOn
14 Hj. Matzke, "On the rim effect in high burnup $UO_2$ LWR fuels", Journal of Nuclear Materials, Vol. 189, 141-148, (1992)   DOI
15 H. Kleykamp, "Solubility of Selected Fission Products in $UO_2$ and (U,Pu)$O_2$", Journal of Nuclear Materials, Vol.206, p.82 (1993)   DOI
16 R.D. Shannon, "Revised Effective Ionic Radii and Systematic Studies of Interatomic Distances in Halides and Chalcogenides", Acta Crystallographica, A 32, p.751, (1976)   DOI
17 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)   DOI