Optimasi Desain Termohidrolika Teras Dan Sistem Pendingin Reaktor Riset Inovatif Daya Tinggi

Hastuti, Endiah Puji; Subekti, Muhammad; Dibyo, Sukmanto; Isnaini, M. Darwis

doi:10.17146/tdm.2015.17.3.2327

Cited by 4 publications

(1 citation statement)

References 9 publications

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“…According to Wardhani's research [13], TRIGA 2000 reactor using plate fuel must use forced cooling. Subekti [14] conducted a study on plate-type fuel in the RSG-GAS reactor, showing that each sub-channel on the fuel-with a 2.55 mm width-has an even distribution of water flow velocity. This means that each fuel meat is being cooled down evenly.…”

Section: Introduction mentioning

confidence: 99%

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Nuryana,

Mahmudah,

Khakim

2023

Atom Indo.

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A novel simulation to calculate the neutronic parameters of the TRIGA 2000 reactor using plate-type fuel has been performed. The plate fuel used was produced by the Indonesian Nuclear Industry (PT INUKI) with U3Si2-Al material. Neutronic parameters based on INUKI’s plate-type fuel dimension and the current TRIGA’s configuration were simulated using MCNPX. The simulation was performed by modeling the complete reactor’s configuration on a fresh fuel core state. We obtained the kinetic parameter values from the simulation, i.e., delayed neutron fraction of 8.11×10‑3, a prompt neutron lifetime of 2.0551×10‑4 s, and an average neutron generation time of 1.87×10‑4 s. The excess reactivity of the reactor was 9.02 %Δk/k, while reactivity in the one-stuck-rod state was below ‑0.5 $ with an average value of ‑3.40 %Δk/k (‑4.19 $). The average thermal neutron flux peak occurred at the central irradiation position with the value of 3.0×1013 to 3.1×1013 n/(cm2 s). The reactor has a power peaking factor of 1.379 in the control rod position of 0 % on D3 fuel. The reactor had a negative feedback reactivity coefficient, except for the moderator coefficient. These results suggest that the current configuration of plate-type fuel met the nuclear reactor neutronic safety standards.

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Section: Introduction mentioning

confidence: 99%

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Nuryana,

Mahmudah,

Khakim

2023

Atom Indo.

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Thermal-hydraulic benchmarking of RSG-GAS research reactor using RELAP5

Hastuti¹,

Ekariansyah²,

Sudarmono³

et al. 2019

AIP Conference Proceedings

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Analysis of oxide fuel element temperature of RSG-GAS by using experiment and calculation

Sudarmono¹,

Bakhri²,

Hastuti³

2021

J. Phys.: Conf. Ser.

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Multipurpose Reactor GA Siwabessy is a research reactor designed to have nominal power of 30 MWth, located in PUSPIPTEK area Serpong and operated by BATAN. RSG GAS utilizes LEU-MTR with enrichment 19.75% and uranium density of 2.96 g U/cm3, 40 fuel rods and 8 control rods, 4 irradiation position (IP) and 1 central irradiation position (CIP) in 2 × 2 lattice, and reactor core surrounded by beryllium reflector. Forced convection cooling mode is applied to remove heat of fission product at normal operation, while natural convection cooling mode is used for reactor physics experiment, or cooling after transient condition. Forced convection cooling mode does not employ primary cooling system, where power is limited to 1% of the nominal power, while natural convection cooling occurs after transient process due to loss of coolant. Heat transfer occurs because of difference in coolant flow density where coolant flows upward since natural circulation valve is opened. This research is aimed to analyze heat removal capability in natural convection cooling mode at the most severe condition following reactor scram. The experiment of cladding and coolant temperature measurement is carried out in fuel coolant channel using instrumented oxide fuel element. Capability of generating reactor power in natural convection cooling is calculated using NATCON code. The measurement result of the highest temperature of plate fuel element is 121°C. Meanwhile, the calculation results of NATCON show that the initial temperature of nucleate boiling TONB occurs at power 685.86 kW and cladding temperature is 126.35 °C. These experiment results indicate that nucleate boiling does not occur in natural convection cooling due to scram or in other words safety margin has been met.

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Optimasi Desain Termohidrolika Teras Dan Sistem Pendingin Reaktor Riset Inovatif Daya Tinggi

Cited by 4 publications

References 9 publications

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Thermal-hydraulic benchmarking of RSG-GAS research reactor using RELAP5

Analysis of oxide fuel element temperature of RSG-GAS by using experiment and calculation

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