journal article·2006-10

Fuel – cladding chemical interaction in MOX fuel rods irradiated to high burnup in an advanced thermal reactor

Kosuke Tanaka, Koji Maeda, Shinji Sasaki, Yoshihisa Ikusawa, Tomoyuki Abe

Journal of Nuclear Materials· Volume 357· Issue 1-3
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Abstract

Abstract The performance of MOX fuel irradiated in the advanced thermal reactor, FUGEN, to a burnup of 47.5 GWd/t, was investigated by using a telescope, optical microscope, SEM and EPMA. Observations focused on elucidating the corrosion behavior of the cladding inner surface. A reaction layer was observed at burnups higher than about 35 GWd/t. The relationship between the thickness of the reaction layer and burnup was similar to that reported in the literature for conventional UO 2 fuel and other MOX fuels. The existence of a plutonium spot near the outer surface of the fuel pellet had no significant effect on the thickness of the reaction layer. A bonding layer was observed on the cladding inner surface. Its morphology and elemental distributions were not so different from those in BWR UO 2 fuel rods irradiated to high burnup, in which the fission gas release rate is high. In addition, the dependences of bonding layer formation on the burnup and linear heat rating were similar to results of UO 2 fuel rods. It was, thus, suggested that the bonding layer formation mechanism was similar in both UO 2 and MOX fuel rods.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing

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References (16)

Show source-provided references
1. S. Maeda, H. Nakazawa, T. Abe, Proceedings of the International Conference on Global Environment and Advanced Nuclear Power Plants, GENES4/ANP2003, Kyoto, Japan, Paper 1150 (2003).
2. T. Ozawa, Y. Ikusawa, T. Abe, K. Maeda, Proceedings of the 2004 International Meeting on LWR Fuel Performance, Orlando, FL, September 19–22, Paper 1031 (2004).
3. Davies · J. Nucl. Mater. · 1971 · 41 · 14310.1016/0022-3115(71)90074-2 ↗
4. Kleykamp · J. Nucl. Mater. · 1985 · 131 · 22110.1016/0022-3115(85)90460-X ↗
5. Koizumi · Nucl. Technol. · 1983 · 61 · 5510.13182/NT83-A33143 ↗
6. K. Asahi, M. Oguma, T. Matsumoto, T. Toyoda, Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance, West Palm Beach, FL, April 17–21 (1994) 726.
7. A. Ohuchi, T. Nomata, S. Koizumi, T. Aoki, IAEA Specialists’ Meeting on Post Irradiation Examination and Experience, Tokyo, Japan, November 26–30 (1984) JA-8.
8. A. Ohuchi, H. Sakurai, Proceedings of ANS Topical Meeting on LWR Fuel Performance, Williamsburg, VA, April (1988) 180.
9. Walker · J. Nucl. Mater. · 1997 · 245 · 16910.1016/S0022-3115(97)00009-3 ↗
10. Deramaix · Nucl. Technol. · 1993 · 102 · 4710.13182/NT93-A34801 ↗
11. Adamson · GEAP-14075 · 1976
12. Nerman · Nucl. Eng. Des. · 1980 · 56 · 28910.1016/0029-5493(80)90194-6 ↗
13. K. Une, K. Nogita, S. Kashibe, T. Toyonaga, M. Amaya, Proceedings of the 1997 International Topical Meeting on LWR Fuel Performance, Portland, OR, March 2–6 (1997) 478.
14. Nogita · J. Nucl. Sci. Technol. · 1997 · 34 · 67910.3327/jnst.34.679 ↗
15. Nogita · IAEA-TECDOC-1036 · 1998 · 377
16. T. Abe, S. Maeda, H. Nakazawa, Proceedings of 13th International Conference on Nuclear Engineering, Beijing, China, May 16–20 (2005) No. 50298.