Evaluating the Use of Graphite and BeO Moderators for Micro Molten Salt Reactor

Authors

  • R. Andika Putra Dwijayanto
  • Almira Citra Amelia
  • Andang Widi Harto

DOI:

https://doi.org/10.4186/ej.2025.29.12.25 Full article

Abstract

Graphite is the most common material proposed as the moderator for thermal molten salt reactor (MSR). Apart from graphite, beryllium oxide (BeO) emerges as an alternative candidate of moderator material which offers superior moderating capability that allows more compact reactor core design. This is important especially for microreactors. This study evaluates the use of graphite and BeO as moderator material in micro-sized MSR. The evaluation encompassed neutronic and burnup calculations, using MCNP6.2 radiation transport code and ENDF/B-VII.0 cross section library. Two alternative fuel options, low-enriched uranium (LEU) and LEU combined with thorium (LEU-Th), were analysed. The moderator options were arranged in three different configurations. From the calculation results, the optimal use of graphite and BeO depends on the fuel option. Whilst BeO shows a glimpse of benefit for LEU-Th fuel option, graphite is a more suitable choice for LEU fuel. The use of BeO in LEU fuel failed to offer longer operational time essential in microreactor, but successfully extended operational time in LEU-Th. Inherent safety aspects and the change of fuel materials over time are also discussed.

Keywords:

micro molten salt reactor, graphite moderator, beryllium oxide, MCNP6.2, ENDF/B-VII.0

Affiliations

  • R. Andika Putra Dwijayanto National Research and Innovation Agency
  • Almira Citra Amelia National Research and Innovation Agency
  • Andang Widi Harto Universitas Gadjah Mada

Corresponding author: R. Andika Putra Dwijayanto, rand002@brin.go.id

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Author Biographies

  • R. Andika Putra Dwijayanto

    Research Centre for Nuclear Reactor Technology, Research Organisation for Nuclear Energy, National Research and Innovation Agency, Building No. 80 BJ Habibie Science and Technology Area, Indonesia

  • Almira Citra Amelia

    Research Centre for Nuclear Reactor Technology, Research Organisation for Nuclear Energy, National Research and Innovation Agency, Building No. 80 BJ Habibie Science and Technology Area, South Tangerang 15314, Indonesia

  • Andang Widi Harto

    Department of Nuclear Engineering and Physics Engineering, Faculty of Engineering, Universitas Gadjah Mada, Jl. Grafika No. 2, Yogyakarta 55281, Indonesia

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How to Cite

[1]
R. A. P. Dwijayanto, A. C. Amelia, and A. W. Harto, “Evaluating the Use of Graphite and BeO Moderators for Micro Molten Salt Reactor”, Eng. J., vol. 29, no. 12, pp. 25–36, Dec. 2025, doi: 10.4186/ej.2025.29.12.25.

Citations

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Published

2025-12-31

Issue

Vol. 29 No. 12 (2025): Regular Issue

Section

Environment, Energy and Natural Resources

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