Neutronic Analysis of the NuScale Fuel Assembly using Accident Tolerant Fuel with SiC Coated Alumina Cladding

Rahmania Serli Assifa, R. Andika Putra Dwijayanto, Fajar Arianto

DOI: http://dx.doi.org/10.55981/tdm.2024.7101

Abstract


Nuclear fuel design is influential on the performance and safety of a nuclear reactor. Accident Tolerant Fuel (ATF) is a novel concept in nuclear fuel technology developed to improve performance and safety of a nuclear power reactor. Different ATF material can impact the neutronic aspect of a nuclear reactor, and thus must be analysed accordingly. This research is a neutronic analysis of an ATF design using alumina (Al2O3) and outer silicon carbide (SiC) coating implemented in NuScale SMR fuel assembly. MCNP6.2 code was utilised to perform neutronic calculation. Standard M5 cladding in NuScale was compared with Al2O3 and Al2O3+ SiC cladding. Analysed parameters were fuel burnup, kinetic parameters, Doppler temperature coefficient, moderator tempereature coefficient, and the evolution of several radionuclides. The results show that there are no significant differences in neutronic performance of Al2O3 clad compared to standard M5 clad. Therefore, Al2O3 cladding is potential for application in PWR fuel.

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References


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