A comparative assessment of independent thermal-hydraulic models for research reactors: The RSG-GAS case

Chatzidakis, Stylianos; Hainoun, A.; Doval, A.; Alhabet, F.; Francioni, F.; Ikonomopoulos, A.; Ridikas, D.

doi:10.1016/j.nucengdes.2013.11.076

Cited by 15 publications

(8 citation statements)

References 8 publications

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“…The cooling water to remove generated heat in the fuel elements flows downward between subchannels inside a fuel element and between sidelines of fuel elements due to forced convection driven by the primary cooling pumps. When the forced convection is lost, the flaps below the core will fall by gravity to enable an upward natural circulation driven by water density difference [12]. Figure 1 below presents the core configuration on the whole, each standard fuel element, each control fuel element, and the flow direction.…”

Section: Description Of Rsg-gas Corementioning

confidence: 99%

“…The reactor cooling pumps of RSG-GAS delivers coolant flow with the total nominal mass flow of 860 kg/sec to enter the subchannel of the fuel plates with the effective mass flow of 618 kg/second on 0.6 m length. The mass flow rate between 2 fuel plates are differently calculated by other researchers and ranged from 0.517 to 0.936 kg/sec [12]. The total power to be generated in the core is 30 MWt providing an average power per plate of 31.25 kWt from 960 fuel plates.…”

Section: Description Of Rsg-gas Corementioning

confidence: 99%

“…To represent the axial distribution along the vertical plate, a value of axial peaking factor of 1.603 is used, which is distributed in 11 axial nodes. Those values and assumption has been used for the comparative assessment of the RSG-GAS reactor [10,12]. The difference is that the hot core is modelled by integrating all 21 fuel plates into one heat structure in which the 22 subchannel flow areas were simplified into one subchannel.…”

Section: Relap5 Nodalization For Severe Accident Analysismentioning

confidence: 99%

“…On each segment, a uniform temperature distribution is applied according to the each axial segment factor respectively. To validate the calculated cladding temperature, measured cladding temperatures from two Instrumented Fuel Elements, IFE RI-10 and IFE RI-11, are provided at several plate positions, in hot and average core as also the positions for inlet and outlet core temperature, in which the values can be seen in References [10,12]. The thermocouple positions are descriptive presented in Table 1 and visually in Figure 2.…”

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confidence: 99%

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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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Section: Description Of Rsg-gas Corementioning

confidence: 99%

Section: Description Of Rsg-gas Corementioning

confidence: 99%

Section: Relap5 Nodalization For Severe Accident Analysismentioning

confidence: 99%

mentioning

confidence: 99%

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Relap5 Simulation for Severe Accident Analysis of RSG-Gas Reactor

Ekariansyah

Hastuti²,

Sudarmono³

2018

Tri Dasa Mega

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“…To study the CARR thermal hydraulic safety characteristics at accident condition due to station blackout, Wenxi Tian et al (2007) conducted an accidental analysis using TSACC code developed [6]. The use of computer codes for calculation such as PARET-ANL, RELAP-5 et cetera has proved that these codes can be used to analyze thermal hydraulic safety at steady state and transient state as carried out by Hamidouche (2009), Omar S. AL-Yahia et al (2013), and Chatzidakis (2014) [7][8][9].…”

Section: Introductionmentioning

confidence: 99%