Maíra Cesário A. Lobo , Marcelo V. Silva , Diego M.E. Gonçalves , João Manoel L. Moreira , Daniel Artur P. Palma , Francky Roger A. da Silva , Giovanni L. de Stefani
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Analysis of fuel alternatives to achieve breeding capability in the FUJI-U3-(0) reactor
In this study, the core physics of the FUJI-U3-(0) small modular molten salt reactor was simulated using the SERPENT code. The cylindrical thermal reactor core was modeled with three concentric regions, each containing distinct fuel channel radii embedded within hexagonal graphite moderator rods. Five molten salt fuel compositions were analyzed, varying the fissile and fertile materials and their respective proportions. After criticality was achieved, key reactor performance metrics, including conversion ratio and waste production, were evaluated. The results led to discussion of the feasibility of a thermal molten salt breeder reactor with different fuel types. Furthermore, APTh1000 and ANGRA-I nuclear waste was incorporated into selected fuel compositions. For APTh1000 waste, an economic assessment of recycled fuel was performed, which revealed that it is more cost-effective and environmentally advantageous compared to fresh fuel.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.