Dispersion type metal-metal based high-density fuels for nuclear reactors – sample preparation, analysis and examination of LOCA behaviour

Metal-based nulear fuels have been proposed as an alternative to UO2 partly in response to increasing pressure to continually improve nuclear system safety. In this work, a set of High-Density Fuel samples manufactured from depleted uranium alloys and Zr-based matrix have been manufactured and evaluated in the as-manufactured and post-LOCA conditions. A qualitative analysis of the samples showed that the matrix and fuel behaviour is mostly consistent with theory and available research while quantitative analysis revealed a major impact of fuel element geometry on packing density and distribution. Fuel–matrix–cladding interactions of varying intensity have also been observed during fabrication and under LOCA conditions.

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Publication Details

Journal
Acta Polytechnica CTU Proceedings
Published
2025-12-29
DOI
https://doi.org/10.14311/app.2025.55.0071
Primary Topic
Nuclear Materials and Properties
Type
article
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article

Dispersion type metal-metal based high-density fuels for nuclear reactors – sample preparation, analysis and examination of LOCA behaviour

Jitka Kabátová, Tomáš Chmela, Jakub Krejčí, Petr Šárek
Acta Polytechnica CTU Proceedings
Nuclear Materials and Properties
article

Dispersion type metal-metal based high-density fuels for nuclear reactors – sample preparation, analysis and examination of LOCA behaviour

Jitka Kabátová, Tomáš Chmela, Jakub Krejčí, Petr Šárek
article en

Abstract

Metal-based nulear fuels have been proposed as an alternative to UO2 partly in response to increasing pressure to continually improve nuclear system safety. In this work, a set of High-Density Fuel samples manufactured from depleted uranium alloys and Zr-based matrix have been manufactured and evaluated in the as-manufactured and post-LOCA conditions. A qualitative analysis of the samples showed that the matrix and fuel behaviour is mostly consistent with theory and available research while quantitative analysis revealed a major impact of fuel element geometry on packing density and distribution. Fuel–matrix–cladding interactions of varying intensity have also been observed during fabrication and under LOCA conditions.

Acta Polytechnica CTU ProceedingsVol. 55
Ujp Praha (Czechia) (CZ), Czech Technical University in Prague (CZ)
Affordable and clean energy
Openalex Percentile: Top 46%
Nuclear Materials and Properties
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