Nuclear Engineering and Design
 2023
DOI: 10.1016/j.nucengdes.2023.112463
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Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle

Fitria Miftasani1,
Nina Widiawati2,
Nuri Trianti3
et al.
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Cited by 3 publications
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State space modelling development of Micro-High-Temperature Gas-Cooled reactor with helium Brayton cycle

Qiu,
Fan,
Liao
et al. 2024
Annals of Nuclear Energy
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State space modelling development of Micro-High-Temperature Gas-Cooled reactor with helium Brayton cycle

Qiu,
Fan,
Liao
et al. 2024
Annals of Nuclear Energy
2
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0
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Pressureless sintering behavior of ZrC ceramic particles encapsulated by nano-sized carbon layer

Zeng,
Zhang,
Fang
et al. 2024
Ceramics International
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Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme

Miftasani,
Andika Putra Dwijayanto,
Abrar
et al. 2024
Nuclear Engineering and Design
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