Analysis of fluid fuel flow to the neutron kinetics on molten salt reactor FUJI-12

Aji, Indarta Kuncoro; Waris, Abdul; Permana, Sidik

doi:10.1063/1.4930795

Cited by 5 publications

(3 citation statements)

References 3 publications

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“…The buoyancy generated by the change in fluid density produced from temperature differences in the momentum equation was set using Boussinesq approximation as written in equation ( 4). Where, 𝜌 0 is the fluid reference density and 𝛽 is the coefficient of thermal expansion at constant pressure as in equation (5).…”

Section: Methodsmentioning

confidence: 99%

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Computational fluid dynamics analysis of the natural circulation system in vertical heater horizontal cooler (VHHC) molten salt loop

Hariyanto¹,

Waris²,

Suprijadi³

2022

J. Phys.: Conf. Ser.

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Molten salt has attracted the attention of researchers, especially as a coolant because of its characteristics. This study aimed to analyse the transient and steady-state of the natural circulation system in the molten salt loop with vertical heater and horizontal cooler using computational fluid dynamics. The computational fluid dynamics module in the COMSOL Multiphysics software was used to solve governing equations. Experimental data from several references were used as input data in modelling. The loop was modelled as a rectangular loop with Inconel 625 as the pipe material and molten salt (NaNO3+KNO3) as the working fluid. The variation of heater power was also carried out in modelling. The modelling results showed a good agreement with the experimental results. The results provided that the molten salt natural circulation loop with vertical heater and horizontal cooler showed good flow stability without reversal of flow direction.

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Section: Methodsmentioning

confidence: 99%

“…One of the advanced nuclear reactors, the molten salt reactor (MSR), utilises a natural circulation system to circulate the fuel as a passive safety design [4]. As reported in papers [5][6][7], the molten salt reactor fuel is molten salt from a mixture of LiF-BeF2-ThF4-(PuMA)F4 or LiF-BeF2-ThF4-233UF4.…”

Section: Introductionmentioning

confidence: 99%

Computational fluid dynamics analysis of the natural circulation system in vertical heater horizontal cooler (VHHC) molten salt loop

Hariyanto¹,

Waris²,

Suprijadi³

2022

J. Phys.: Conf. Ser.

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“…One of the advanced nuclear reactors that implemented the natural circulation system to circulate its fuel as a passive safety design is the Molten Salt Reactor 14,15 . As reported in papers, 16‐19 the fuel of Molten Salt Reactor is molten salt from a mixture of LiF‐BeF 2 ‐ThF 4 ‐(PuMA)F 4 or LiF‐BeF 2 ‐ThF 4 ‐ 233 UF 4 . Where, Thorium fuel ( 232 Th) provides an advantage for safety factors in reactor operations related to the void condition 20‐23 …”

Section: Introductionmentioning

confidence: 99%

Experimental and simulation approach of the loop geometry effect on the natural circulation system of the advanced nuclear reactor

2020

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Summary Lately, natural circulation has become an exciting topic because it has been proposed and applied in some advanced nuclear reactors as a passive safety system. The aim of the present study is to examine the effect of the loop geometry on the natural circulation based cooling system of a given power source. The experimental approach was achieved by the construction of two natural circulation loops with vertical heater and vertical cooler. Both circulation loops were built with a same vertical length of 100 cm and different horizontal lengths, each of 50 and 100 cm, respectively. The heater was realized with a stainless pipe wrapped by a Nichrome wire, whereas the cooling system was designed and built as a pipe in 30 cm long square tube. Thus, the cooling water will circulate around the pipe loop inside the rectangular cooling chamber. The temperature data acquisition was achieved via an Arduino‐based system, controlling four K‐type thermocouple sensors. The numerical simulation part in the present work, was carried out by the COMSOL Multiphysics software, using the dedicated heat transfer and fluid dynamic module, namely the computational fluid dynamic module. The experimental data were considered to parameterize the COMSOL input model. The experimental results showed a clear difference between two passive cooling loops according to the horizontal length. The doublings of the horizontal and vertical lengths of the loop have a direct effect on the fluid flow rate.

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Nitrate salt phase transition study for molten salt loop working fluid consideration

Hariyanto,

Permana,

Waris

et al. 2023

Heat Mass Transfer

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Analysis of fluid fuel flow to the neutron kinetics on molten salt reactor FUJI-12

Cited by 5 publications

References 3 publications

Computational fluid dynamics analysis of the natural circulation system in vertical heater horizontal cooler (VHHC) molten salt loop

Computational fluid dynamics analysis of the natural circulation system in vertical heater horizontal cooler (VHHC) molten salt loop

Experimental and simulation approach of the loop geometry effect on the natural circulation system of the advanced nuclear reactor

Nitrate salt phase transition study for molten salt loop working fluid consideration

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