Simulation of Modified TRIGA-2000 with Plate-Type Fuel under LOFA Using EUREKA2/RR-Code

Dibyo, Sukmanto; Sudjatmi, K.S.; Sihana, S; Irianto, Ign. Djoko

doi:10.17146/aij.2018.541

Cited by 10 publications

(9 citation statements)

References 8 publications

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“…(1) While the previous core design has no AT in the CIP design, it was used as a basis to study thermal hydraulics of PTRRB [16][17][18]. Installation of AT for irradiation at CIP will affect coolant flow.…”

Section: Resultsmentioning

confidence: 99%

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Bahrum¹,

Handiaga²,

Setiadi³

et al. 2020

Tri Dasa Mega

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One of the results from Plate Type Research Reactor Bandung (PTRRB) research program is PTRRB core design. Previous study on PTRRB has not calculated neutron flux distribution at its central irradiation position (CIP). Distribution of neutron flux at CIP is of high importance especially in radioisotope production. In this study, CIP was modeled as a stack of four to five aluminum tubes (AT), each filled by four aluminum irradiation capsules (AIC). Considering AIC dimension and geometry, there are three possibilities of AT configuration. For irradiation sample, 1.45 gr of molybdenum (Mo) was put into AIC. Neutron flux distribution at Mo sample was calculated using TRIGA MCNP and MCNP software. The calculation was simulated at condition when fresh fuel is loaded into reactor core. Analyses of excess reactivity show that, after installing irradiation AT and Mo sample was put into each configuration, the excess reactivity is less than 10.9 %. The highest calculated thermal neutron flux at Mo sample is 5.08×1013 n/cm2.s at configuration 1. Meanwhile, the highest total neutron flux at Mo sample is located at capsule no. II and III. Thermal neutron flux profile is the same for all configurations. This result will be used as a basic data for PTRRB utilization.Keywords: Central Irradiation Position, Neutron Flux Distribution, MCNP, PTRRB

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Section: Resultsmentioning

confidence: 99%

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Bahrum¹,

Handiaga²,

Setiadi³

et al. 2020

Tri Dasa Mega

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“…Whereas RELAP5 code is also used for IAEA 10MW [10]. As comparison, analysis of LOFA on research reactor have been conducted for IEA-R1 and TRIGA reactors by using EUREKA-2/RR [2,11].…”

Section: Introduction *mentioning

confidence: 99%

Transient Analysis of Simultaneous Lofa and Ria in RSG-Gas Reactor After 32 Years Operation

2020

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During the operation of the research reactor RSG-GAS, there are many design parameters should be verified based on postulated accidents. Several design basis accidents (DBA) such as loss of flow accident (LOFA) and reactivity-initiated accident (RIA) also have been conducted separately. This paper discusses about possibility of simultaneous accidents of LOFA and RIA. The accident analyses carry out calculation for transient condition during RIA, LOFA, and postulated accident of simultaneous LOFA-RIA. This study aims to conduct a safety analysis on simultaneous LOFA and RIA, and investigate the impact on safety margins. The calculations are conducted by using the PARET code. The maximum temperature of the center fuel meat at nominal power of 30 MW and steady state conditions is 126.10°C and MDNBR of 2.94. At transients condition, the maximum center fuel meat temperature for LOFA, RIA and simultaneous LOFA-RIA are consecutively 132.99°C, 135.67°C and 138.21°C, and the time of reactor trip are 3.2593s, 3.6494s and 2.7118s, respectively. While the MDNBR for LOFA, RIA and simultaneous LOFA-RIA are respectively at transient condition are 2.88, 2.58 and 2.63, respectively. It is shown that, simultaneous LOFA-RIA has the fastest trip time. In this case, the low flow trip occurs first in advance to over power trip. From these results, it can be concluded that the RSG-GAS has adequate safety margin against transient of simultaneous LOFA-RIA.Keywords: RSG-GAS, Simultaneous, LOFA, RIA, PARET

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“…Calculation of neutronic, kinetic, and incore fuel management parameters as well as thermodynamic parameters in steady-state conditions have been carried out [5][6][7][8]. Based on the calculation results, the conversion core with 2 MW of nominal power requires an additional flow rate in the core [9], but the nominal power of 1 MW can use the current flow rate.…”

Section: Introductionmentioning

confidence: 99%

Analysis of Uncontrolled Reactivity Insertion Transient of Triga Mark 2000 Bandung Using MTR Plate Type Fuel Element

Pinem

Surbakti

Kuntoro

2020

gnd

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ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE TYPE FUEL ELEMENT. Analysis of uncontrolled reactivity insertion is very important for the safety of reactor operations. Determination of melting point limit, critical heat fluxes and melting temperatures of cladding are the main objectives for most of these studies to determine whether fuel temperature can withstand the transient insertion of reactivity. In this study, uncontrolled reactivity insertion transient was carried out due to the withdrawal of control rods in nominal power of 1 MW and 2 MW. Analysis of reactivity transient was carried out using the WIMSD/5B and MTRDYN codes. The WIMSD/5B code is used to generate cross sections and the MTRDYN program is used for analysis under transient conditions. Based on calculations on the initial power of 1 MW and 2 MW with an insertion of reactivity of greater than 0.5 $/s the reactor operation is not safe because the fuel temperature exceeds the design limit. For reactivity insertion 0.5 $/s allows increased power can be stabilized by feedback reactivity. For 1 MW of nominal power, the maximum coolant temperature, cladding and fuel are 86.39 oC, 164.86 oC and 165.33 oC, respectively. For 2 MW of nominal power, the maximum coolant temperature, cladding and fuel are 89.09 oC, 176.96 oC and 177.602 oC, respectively. Based on calculation, It is concluded that the feedback mechanism can protect the fuel cladding from a local meltdown if reactivity insertion 0.5 $/s and the reactor is in nominal power of 1 MW and 2 MW.

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Simulation of Modified TRIGA-2000 with Plate-Type Fuel under LOFA Using EUREKA2/RR-Code

Cited by 10 publications

References 8 publications

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Transient Analysis of Simultaneous Lofa and Ria in RSG-Gas Reactor After 32 Years Operation

Analysis of Uncontrolled Reactivity Insertion Transient of Triga Mark 2000 Bandung Using MTR Plate Type Fuel Element

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