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dc.contributor.authorDwijayanto, R. Andika Putra
dc.contributor.authorArdiansyah, Harun
dc.contributor.authorHarto, Andang Widi
dc.date.accessioned2024-12-24T19:15:34Z
dc.date.available2024-12-24T19:15:34Z
dc.date.copyright4/17/2024 12:00:00 AM
dc.date.issued2024
dc.identifier.issn2332-8983
dc.identifier.otherners_010_03_031301.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4303600
dc.description.abstractThermal molten salt reactors can be designed in many configurations. This paper investigates the optimal geometry of a one fluid molten salt reactor (OFMSR) in a virtual one-and-half fluid configuration with a fixed fuel salt volume. Two primary configurations were studied, axial blanket (three models) and radial blanket (two models). Neutronic calculations were performed using Monte Carlo N-particle 6.2 (MCNP6.2) and Serpent-2 reactor physics codes with evaluated nuclear data files/B-VII.0 continuous neutron library. The analysis comprises criticality calculation, temperature coefficient of reactivity (TCR), breeding ratio (BR), and kinetic parameters. The results imply a good agreement between MCNP and Serpent calculations. TCR values show a different pattern between axial and radial blanket configuration. While the correlation between TCR and BR is inversely correlated in axial blanket, it is linear in radial blanket configuration. Overall, radial blanket configuration seemed to show better neutronic performance than axial blanket configuration, with comparably strong negative TCR and large BR.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleVerification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
dc.typeJournal Paper
dc.journal.volume10
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4064465
dc.journal.fristpage31301-1
dc.journal.lastpage31301-7
dc.page7
dc.treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003
dc.contenttypeFulltext


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