Abstract
The radial distribution of the power, the isotope distributions, and other properties of the UO2 and MOX fuel in the PWR are investigated with the increasing average burnup through the continuous-energy Monte Carlo code TRIPOLI-4. The local burnup phenomena mainly come from the high (n, γ) reaction rates of 238U and 240Pu near the surface of the fuel rod because of the self-shielding mechanism. The present Monte Carlo study shows that the local burnup and cumulative 239Pu near the surface are much larger compared with those at the center of the fuel rod. The local burnup and the isotope distributions are investigated up to 45 MWd/kgU in UO2 fuel and 84 MWd/kgU in MOX fuel.
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Acknowledgments
The authors acknowledge our collaborator CEA for the authorization of the TRIPOLI-4. This work has been supported by the National Natural Science Foundation of China under Grant No. 11305272, the Specialized Research Fund for the Doctoral Program of Higher Education under Grant No. 20130171120014, the Guangdong Natural Science Foundation under Grant No. 2014A030313217, the Pearl River S&T Nova Program of Guangzhou under Grant No. 201506010060, and the Fundamental Research Funds for the Central Universities under Grant No. 14lgpy29.
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Yuan, C., Chen, S., Wang, X. (2017). Monte Carlo Study on Radial Burnup and Isotope Distribution. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2314-9_14
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DOI: https://doi.org/10.1007/978-981-10-2314-9_14
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