Steady-state thermal-hydraulic analysis of the TRIGA plate core design by using COOLOD-N2 and RELAP5 codes

Widodo, Surip; Hastuti, Endiah Puji; Alfa, Sudjatmi Kustituantini; Nazar, Reinaldy

doi:10.1063/1.5135526

Cited by 3 publications

(2 citation statements)

References 9 publications

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“…Therefore, one dimension of the COOLOD-N2 code is used to calculate the steady-state at unblocked conditions. The COOLOD-N2 is a computer code for the analyses of steady-state thermal-hydraulics of both the rod-type and plate-type fuels [19,20]. In this study, it is assumed that the blocked sub-channel was the hottest channel in the core.…”

Section: Resultsmentioning

confidence: 99%

CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core

et al. 2022

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A nuclear reactor cooling system that has been operating for a long time can carry some debris into a fuel coolant channel, which can result in a blockage. An in-depth two-dimensional simulation of partial channel blockage can be carried out using FLUENT Code. In this study, a channel blockage simulation is employed to perform a safety analysis for the TRIGA-2000 reactor, which is converted using plate-type fuel. Heat generation on the fuel plate takes place along its axial axis. The modelling of the fuel-plate is in the form of a rectangular sub-channel with an inlet coolant temperature of 308 K with a low coolant velocity of 0.69 m/s. It is assumed that blockage is in a form of a thin plate, with the blockage area being assumed to be 60 %, 70 %, and 80 % at the sub-channel inlet flow. An unblocking condition is also compared with a steady-state calculation that has been done by COOLOD-N2 Code. The results show that a partial blockage has a significant impact on the coolant velocity. When the blockage of 80 % occurs, a maximum coolant temperature locally reaches 413 K. While the saturation temperature is 386 K. From the point of view of the safety aspect, the blockage simulation result for the TRIGA-2000 thermal-hydraulic core design using plate-type fuel shows that a nucleate boiling occurs, which from the safety aspect, could cause damage to the fuel plate.

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Section: Resultsmentioning

confidence: 99%

CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core

et al. 2022

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“…The cooling system is equipped with 1 heat exchanger unit, and 2 cooling tower units. Meanwhile, in case the reactor is operated at a power of 2 MW using a plate-type fuel element, at least a mass flow rate of 70 kg/s is required [6] . Otherwise, the evaluation results do not recommend two primary coolant pump units to flow the coolant needed to take heat from the reactor [8][9] .…”

Section: Introductionmentioning

confidence: 99%

Steady-State Analysis on Coolant System Operating of the Triga2000 Using Fuel Plate Type

Dibyo¹

2021

bprn

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STEADY-STATE ANALYSIS ON COOLANT SYSTEM OPERATING OF THE TRIGA2000USING FUEL PLATE TYPE. The TRIGA2000 is one of the nuclear research reactors in Indonesia. TRIGA reactor fuel element is rod type, studies of the TRIGA reactor using plate type fuel have been carried out. One primary coolant pump is required to overcome the safety factor on the core which uses plate-type fuel. Besides that, changes in the reactor core configuration have an effect on the ability to transfer heat from the core to the coolant. Therefore, it is necessary to analyze the operating parameters of the cooling system including temperature, pressure and flow rate. This operating data is important, which is required by the operator to estimate the reactor coolant condition. The purpose of this paper is to analyze the cooling system parameters under normal steady-state operation where the primary coolant capacity is 50 kg/s and the reactor power is determined to be 1 MW. Calculation of cooling system at normal condition is carried out using the ChemCAD.6.1.4 computer program. This is also required in providing the reactor's Safety Analysis Report (SAR) document. The results show that the TRIGA reactor which uses plate-type fuel elements can be operated safely. However, in case of coolant temperature to the reactor core exceeding the design data (35 o C), it is necessary to be considered against the operational reliability of the cooling system.

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Analysis of DNBR TRIGA 2000 calculation results using STAT and COOLOD-N2

Alfa¹,

Basuki²

2021

Proceedings of International Conference on Nuclear Science, Technology, and Application 2020 (Iconsta 2020)

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Steady-state thermal-hydraulic analysis of the TRIGA plate core design by using COOLOD-N2 and RELAP5 codes

Cited by 3 publications

References 9 publications

CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core

CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core

Steady-State Analysis on Coolant System Operating of the Triga2000 Using Fuel Plate Type

Analysis of DNBR TRIGA 2000 calculation results using STAT and COOLOD-N2

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