Main Article Content
Abstract
The Hydride–Dehydride (HDH) method is a critical technology in uranium processing, capable of improving the efficiency and quality of nuclear fuel through a more precise embrittlement process compared to conventional techniques. This technology ensures uniform particle size and minimizes material loss during fabrication. This study was conducted using a literature review approach, supported by experimental data obtained during a 2022 internship at the Research Center for Nuclear Fuel Cycle and Radioactive Waste Technology (PRTDBBLNR). The focus of the investigation was the characterization of uranium–molybdenum (U-Mo) alloy before and after the HDH treatment process. The results indicate that heat treatment at 500 °C for 5 hours followed by annealing significantly increases the hardness of the U-Mo alloy. A phase transformation was also observed, indicated by the presence of α-U in all post-treatment samples. Nevertheless, the density of the alloy showed no substantial change. The HDH process successfully produced high-purity U-Mo powder at various molybdenum concentration levels. However, increasing Mo content resulted in lower powder density. The morphology of U-7Mo powder exhibited flake-like shapes with a rough surface, which is favorable for further fabrication in advanced fuel element production. Overall, these findings reinforce the relevance and significant potential of HDH technology in supporting advanced nuclear reactor fuel production and strengthening national nuclear energy security in a sustainable manner.The Hydride–Dehydride (HDH) method represents an important innovation in uranium processing to improve the efficiency and quality of nuclear fuel. This technology enables a more precise embrittlement of uranium compared to conventional methods such as milling and crushing, resulting in more uniform particle size and reduced material loss throughout the process. This study adopts a literature-based approach supported by practical work conducted at the Center for Research on Nuclear Fuel Cycle Technology and Radioactive Waste Management (PRTDBBLNR) in 2022, in order to evaluate the effectiveness of HDH in strengthening nuclear energy security in Indonesia. The analysis shows that HDH improves the microstructural quality of uranium and enhances processing yield by minimizing waste generation. These advantages highlight the high relevance of HDH technology in supporting the development of Generation IV nuclear reactors, which emphasize efficiency and sustainability within the fuel cycle. However, its implementation in Indonesia still faces challenges, particularly in terms of industrial infrastructure readiness, safety regulations, and nuclear material protection. Therefore, strategic policies are required to promote further research and technological investment, as well as strong collaboration between academia, government, and industry. Integrating HDH into the national uranium processing roadmap has the potential to establish this technology as a key pillar in ensuring a sustainable nuclear fuel supply and enhancing Indonesia’s energy security in the future.
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Copyright (c) 2025 Zafira Naja Sakina, Fakhriyan Ardyanto, Imam Supriyadi, Budi Santoso
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This work is licensed under a Creative Commons Attribution-ShareAlike 4.0 International License.
References
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- Balart, S., Bruzzoni, P., Granovsky, M., Gribaudo, L., & Hermida, J. (2000). U-Mo alloy powder obtained by a hydride-dehydride process. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Las Vegas, Nevada.
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- Clark, C. R., Meyer, M. K., & Strauss, J. T. (1998). Fuel powder production from ductile uranium alloys. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Sao Paulo, Brazil.
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- Ganisa, et al. (2019). Karakterisasi serbuk paduan U-Mo hasil proses hydride–dehydride sebagai kandidat bahan bakar reaktor riset nuklir. Universitas Gadjah Mada.
- Havela, L., & Ngan, N. T. H. K. (2017). Hydrogen absorption in uranium-based alloys with cubic γ-U structure. Advances in Natural Sciences: Nanoscience and Nanotechnology.
- International Atomic Energy Agency. (2009). Good practices for qualification of high-density low enriched uranium research reactor fuels. IAEA.
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- Neto, R. M. L., Rocha, C. J., Carvalho, E. U., Riella, H. G., & Durazzo, M. (2014). Investigation of powdering ductile gamma U-10 wt.% Mo alloy for dispersion fuels. Journal of Nuclear Materials, 445, 218–223.
- Oliveira, F. B. V., Riella, H. G., & Durazzo, M. (2006). Gamma-molybdenum alloys behavior under hydrogen atmosphere. 7° CBECIMat - Congresso Brasileiro de Engenharia e Ciência dos Materiais.
- Oliveira, F. B. V., & Riella, H. G. (2008). Hydrogen absorption–desorption and gamma-UMo nuclear fuel powder production. Materials Science Forum, 591–593, 201–205.
- Supardjo. (2007). Studi proses pembuatan serbuk UMo sebagai bahan bakar dispersi UMo-Al untuk reaktor riset. Prosiding PPI-PDIPTN, 217–223.
- Supardjo. (2014). Pengenalan bahan bakar reaktor riset. Diklat Teknologi Fabrikasi Bahan Bakar Reaktor Riset.
- Supardjo, & Masrukan. (2008). Pembuatan dan karakterisasi paduan U-Mo sebagai kandidat bahan bakar nuklir tipe dispersi. Jurnal Teknologi Bahan Nuklir, 4(2), 48–57.
- Yemel’yanov, V. S., & Yevstyukhin, A. I. (1969). The metallurgy of nuclear fuel: Properties and principles of the technology of uranium, thorium and plutonium. Pergamon Press.
- Zhang, X., Yang, Z., Meng, Y., Kang, S., & He, J. (2017). Influence of Mo content on the γ-U phase stability and properties of U-Mo alloy. IOP Conference Series: Materials Science and Engineering, 182, 01202.
References
Berghe, S. V., & Lemoine, P. (2014). Review of 15 years of high-density low-enriched UMo dispersion fuel development for research reactors in Europe. Nuclear Engineering and Technology, 46(2), 125–146.
Balart, S., Bruzzoni, P., Granovsky, M., Gribaudo, L., & Hermida, J. (2000). U-Mo alloy powder obtained by a hydride-dehydride process. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Las Vegas, Nevada.
Creasy, J. T. (2011). Thermal properties of uranium-molybdenum alloys: Phase decomposition effects of heat treatment [Master’s thesis, Texas A&M University].
Clark, C. R., Meyer, M. K., & Strauss, J. T. (1998). Fuel powder production from ductile uranium alloys. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Sao Paulo, Brazil.
Chen, M., Xiong, Y. F., Jing, W. Y., Jia, J. P., & Zhang, P. C. (2010). Characterization of γ-U-10 wt.% Mo alloy powders obtained by hydride–milling–dehydride process. Journal of Nuclear Materials, 400(1), 69–72.
Garnetti, D. J. (2009). Uranium powder production via hydride formation and alpha phase sintering of uranium–zirconium alloys for advanced nuclear fuel applications [Master’s thesis, Texas A&M University].
Ganisa, et al. (2019). Karakterisasi serbuk paduan U-Mo hasil proses hydride–dehydride sebagai kandidat bahan bakar reaktor riset nuklir. Universitas Gadjah Mada.
Havela, L., & Ngan, N. T. H. K. (2017). Hydrogen absorption in uranium-based alloys with cubic γ-U structure. Advances in Natural Sciences: Nanoscience and Nanotechnology.
International Atomic Energy Agency. (2009). Good practices for qualification of high-density low enriched uranium research reactor fuels. IAEA.
Kim, Y. S. (2012). Uranium intermetallic fuels (U–Al, U–Si, U–Mo). Elsevier Inc.
Neto, R. M. L., Rocha, C. J., Carvalho, E. U., Riella, H. G., & Durazzo, M. (2014). Investigation of powdering ductile gamma U-10 wt.% Mo alloy for dispersion fuels. Journal of Nuclear Materials, 445, 218–223.
Oliveira, F. B. V., Riella, H. G., & Durazzo, M. (2006). Gamma-molybdenum alloys behavior under hydrogen atmosphere. 7° CBECIMat - Congresso Brasileiro de Engenharia e Ciência dos Materiais.
Oliveira, F. B. V., & Riella, H. G. (2008). Hydrogen absorption–desorption and gamma-UMo nuclear fuel powder production. Materials Science Forum, 591–593, 201–205.
Supardjo. (2007). Studi proses pembuatan serbuk UMo sebagai bahan bakar dispersi UMo-Al untuk reaktor riset. Prosiding PPI-PDIPTN, 217–223.
Supardjo. (2014). Pengenalan bahan bakar reaktor riset. Diklat Teknologi Fabrikasi Bahan Bakar Reaktor Riset.
Supardjo, & Masrukan. (2008). Pembuatan dan karakterisasi paduan U-Mo sebagai kandidat bahan bakar nuklir tipe dispersi. Jurnal Teknologi Bahan Nuklir, 4(2), 48–57.
Yemel’yanov, V. S., & Yevstyukhin, A. I. (1969). The metallurgy of nuclear fuel: Properties and principles of the technology of uranium, thorium and plutonium. Pergamon Press.
Zhang, X., Yang, Z., Meng, Y., Kang, S., & He, J. (2017). Influence of Mo content on the γ-U phase stability and properties of U-Mo alloy. IOP Conference Series: Materials Science and Engineering, 182, 01202.