INVESTIGATION OF DEPLETED Np FOR THE CERTAIN NEPTUNIUM MIXED FUELS


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Authors

  • Mehtap DÜZ İnönü University, Faculty of Arts and Sciences, Department of Physics, Malatya
  • Selcan İNAL İnönü University, Institute of Science, Malatya

DOI:

https://doi.org/10.38065/euroasiaorg.508

Keywords:

BWR, depletion mass, MCNPX-2.7.0, ENDF/B-VII.0

Abstract

In this study, three-dimensional boiling water reactor (BWR) modeling is designed using MCNPX-2.7.0 Monte Carlo method and ENDF/B-VII.0 nuclear data library. In the designed BWR, NpO2 and NpF4 fuel rods were used as fuel, Zr-2 and SiC as fuel cladding, and H2O as cooler. In the designed BWR modeling, it was observed that as the percentage of neptunium mixed fuel increased, the percentages of depleted Np increased. As a result of the calculations, it was concluded that SiC clad and NpO2 fuel rod are more suitable for the amount of depletion in the BWR reactor.

Published

2021-06-06

How to Cite

DÜZ, M., & İNAL, S. (2021). INVESTIGATION OF DEPLETED Np FOR THE CERTAIN NEPTUNIUM MIXED FUELS. Euroasia Journal of Mathematics, Engineering, Natural & Medical Sciences, 8(15), 12–22. https://doi.org/10.38065/euroasiaorg.508

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Section

Articles