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contributor authorDwijayanto, R. Andika Putra
contributor authorArdiansyah, Harun
contributor authorHarto, Andang Widi
date accessioned2024-12-24T19:15:34Z
date available2024-12-24T19:15:34Z
date copyright4/17/2024 12:00:00 AM
date issued2024
identifier issn2332-8983
identifier otherners_010_03_031301.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4303600
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.
publisherThe American Society of Mechanical Engineers (ASME)
titleVerification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
typeJournal Paper
journal volume10
journal issue3
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4064465
journal fristpage31301-1
journal lastpage31301-7
page7
treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003
contenttypeFulltext


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