Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code

Karimpour, M. H.; Esteki, Mohammad Hossein

doi:10.1016/j.pnucene.2014.11.006

Cited by 7 publications

(2 citation statements)

References 4 publications

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“…The number of channels in the core was also found to be important to refine the calculation results (Reis et al, 2012). Other studies assessed several thermalhydraulic codes, including RELAP5, against an MTR-type reactor for a steady state condition, loss of flow, and loss of coolant transient (Abdelrazek et al, 2014;Chatzidakis et al, 2014;Chatzidakis et al, 2013;Hedayat et al, 2007;Karimpour & Esteki, 2015). In those studies, the RELAP5 code was generally able to simulate the steady state condition with good agreement but with a higher discrepancy during the transient considered in the study.…”

Section: Introductionmentioning

confidence: 99%

TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

Antariksawan¹,

Umar²,

Widodo³

et al. 2017

IJTech

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Any events presumed to risk the safety of a nuclear reactor should be analyzed. In a research reactor, the applicability of best estimate thermal-hydraulic codes has been assessed for safety analysis purposes. In this paper, the applicability of the RELAP/SCDAPSIM/MOD3.4 thermalhydraulic code to one Indonesian research reactor, which is named TRIGA-2000, is performed. The aim is to validate the model and use the model to analyze the thermal-hydraulic characteristics of TRIGA-2000 for main transient events considered in the Safety Analysis Report. The validation was done by comparing the calculation results with experimental data mainly in steady state conditions. The comparison of calculation results with the measurement data showed good agreement with little discrepancies. Based on these results, simulations for thermal-hydraulic analyses were performed for loss of coolant transients. The calculation results also properly depicted the physic of the thermal-hydraulic phenomena following the loss of coolant transients. These results showed the adequacy of the model. It could be shown that the engineered safety features of TRIGA-2000 play an important role in keeping the reactor safe from the risk of postulated loss of a coolant accident.

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Section: Introductionmentioning

confidence: 99%

TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

Antariksawan¹,

Umar²,

Widodo³

et al. 2017

IJTech

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“…In reality, that thermal power is not evenly distributed on all 960 plates, since an averaged distributed heat will result in inaccuracy of the calculated plate temperature. Practically, the core is divided into 3 major channels, representing the parallel coolant channels of the different fuel elements, which are the hot, average, and bypass channel [14]. The hot channel represents the fuel element channel, in which the maximum core temperature or the hottest fuel plate can occur, and the average channel represents the fuel element with the average core temperature.…”

Section: Relap5 Nodalization For Severe Accident Analysismentioning

confidence: 99%

Relap5 Simulation for Severe Accident Analysis of RSG-Gas Reactor

Ekariansyah

Hastuti²,

Sudarmono³

2018

Tri Dasa Mega

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RELAP5 SIMULATION FOR SEVERE ACCIDENT ANALYSIS OF RSG-GAS REACTOR.The research reactor in the world is to be known safer than power reactor due to its simpler design related to the core and operational chararacteristics. Nevertheless, potential hazards of research reactor to the public and the environment can not be ignored due to several special features. Therefore the level of safety must be clearly demonstrated in the safety analysis report (SAR) using safety analysis, which is performed with various approaches and methods supported by computational tools. The purpose of this research is to simulate several accidents in the Indonesia RSG-GAS reactor, which may lead to the fuel damage, to complement the severe accident analysis results that already described in the SAR. The simulation were performed using the thermal hydraulic code of RELAP5/SCDAP/Mod3.4 which has the capability to model the plate-type of RSG-GAS fuel elements. Three events were simulated, which are loss of primary and secondary flow without reactor trip, blockage of core subchannels without reactor trip during full power, and loss of primary and secondary flow followed by reactor trip and blockage of core subchannel. The first event will harm the fuel plate cladding as showed by its melting temperature of 590 °C. The blockage of one or more subchannels in the one fuel element results in different consequences to the fuel plates, in which at least two blocked subchannels will damage one fuel plate, even more the blockage of one fuel element. The combination of loss of primary and secondary flow followed by reactor trip and blockage of one fuel element has provided an increase of fuel plate temperature below its melting point meaning that the established natural circulation and the relative low reactor power is sufficient to cool the fuel element.Keywords: loss of flow, blockage, fuel plate, RSG-GAS, RELAP5 ABSTRAK SIMULASI RELAP5 UNTUK ANALISIS KECELAKAAN PARAH PADA REAKTOR RSG-GAS. Reaktor riset di dunia diketahui lebih aman dari pada reaktor daya karena desainnya yang lebih sederhana pada teras dan karakteristika operasinya. Namun demikian, potensi bahaya reaktor riset terhadap publik dan lingkungan tidak bisa diabaikan karena beberapa fitur tertentu. Oleh karena itu, level keselamatan reaktor riset harus jelas ditunjukkan dalam Laporan Analisis Keselamatan (LAK) dalam bentuk analisis keselamatan yang dilakukan dengan berbagai macam pendekatan dan metode dan didukung dengan alat komputasi. Tujuan penelitian ini adalah untuk mensimulasikan beberapa kecelakaan parah pada reaktor RSG-GAS yang dapat menyebabkan kerusakan bahan bakar untuk memperkuat hasil analisis kecelakaan parah yang sudah ada dalam LAK. Simulation dilakukan dengan program perhitungan RELAP5/SCDAP/Mod3.4 yang memiliki kemampuan untuk memodelkan elemen bahan bakar tipe pelat di RSG-GAS. Tiga kejadian telah disimulasikan yaitu hilangnya aliran primer dan

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Transient analyses of the Jordanian 5 MW research reactor under LOEP accident

Al-Yahia

Lee

2016

Annals of Nuclear Energy

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Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code

Cited by 7 publications

References 4 publications

TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

Relap5 Simulation for Severe Accident Analysis of RSG-Gas Reactor

Transient analyses of the Jordanian 5 MW research reactor under LOEP accident

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