Core conversion design study of TRIGA Mark 2000 Bandung using MTR plate type fuel element

Pinem, Surian; Sembiring, Tagor Malem; Surbakti, TS Tukiran

doi:10.1504/ijnest.2018.095689

Cited by 19 publications

(31 citation statements)

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“…This value will be needed to determine the set point in the reactor protection system. The thermalhydraulic analysis on forced convection is calculated using COOLOD-N2 code with still accommodating the coolant flow rate capability of the Bandung TRIGA reactor, while the neutronic design is performed by the core calculation group [12].…”

Section: Introduction *mentioning

confidence: 99%

Analysis on the Performance of the Bandung Conversion Fuel-Plate Triga Reactor in Steady State With Constant Coolant Flow Rate

2020

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Bandung TRIGA2000 Reactor, a General Atomic (GA)-made research reactor used for training, research andiIsotope production, has been upgraded to operate at power of 2000 kW using TRIGA fuel rod type. Recently, the TRIGA reactor fuel element producers are going to discontinue the production of TRIGA fuel element. To overcome the unavailability of TRIGA fuel element, BATAN planned to modify TRIGA2000 fuel type from rod-type to U3Si2-Al plate-type fuel with 19.75% enrichment, similar to the domestically fabricated one used in RSG-GAS. The carried out design emphasized on the determination of operation condition limits for setting the reactor protection system in accordance to the reactor safety calculation results. The conceptual design of the innovative fuel plate TRIGA reactor cooling system is expected to remove heat generated by fuels with nominal power of 1 MW up to 2 MW. The design is developed through modelling and safety analysis using COOLOD-N2 validated code. The safety margin is set to its flow instability at transient condition of the fuel plate, which is ≥ 2.38; departure from nucleate boiling ratio ≥1.50; and no onset of nucleate boiling, ΔTONB ≥ 0oC. The primary coolant flow rate accommodating the existing Bandung TRIGA reactor capability is as high as 50 kg/s. The analysis results show that at power of 1 MW, the reactor can safely operate, while at power of 2 MW the safety margin is exceeded. In other words, the plate TRIGA reactor that employs forced convection mode operates safely at 1 MW with excess power 120% of its nominal power.Keywords: 1 MW, Thermalhydraulic design, Steady state condition, TRIGA plate, Constant flowrate

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Section: Introduction *mentioning

confidence: 99%

Analysis on the Performance of the Bandung Conversion Fuel-Plate Triga Reactor in Steady State With Constant Coolant Flow Rate

2020

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“…The equilibrium core configuration is obtained using 16 fuel elements and 4 control elements [3,4]. 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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“…For this reason, the calculation of the equilibrium core configuration has been carried out using the Batan-FUEL code [1]. The calculation results show that the reactor can be operated at a nominal power of 2 MW using 16 fuels and 4 control rods [2][3][4]. One of the important problems with nuclear reactor operation is safety.…”

Section: Introductionmentioning

confidence: 99%

Neutronic and Thermal Hydraulics Analysis of Control Rod Effect on the Operation Safety of Triga 2000 Reactor

Pinem¹,

Surbakti²,

Kuntoro³

2019

urania

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NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR.Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation. During the reactor operation cycle, the position of the control rods will change due to reactivity changes. The purpose of this study is to determine the effect of control rods position on neutronic and thermal-hydraulics parameters in relation to the safety of reactor operation of the TRIGA 2000 reactor using silicide fuel of MTR plate type. Those parameters are power peaking factor, reactivity coefficients, and steady-state thermohydraulic parameters. Neutronic calculations are performed using a combination of WIMSD/5 and Batan-3DIFF codes and for thermal-hydraulics the calculations are done using WIMSD/5 and MTRDYN codes. The calculation results show that the reactivity coefficient values are negative for all control rod positions both at CZP and HFP conditions. The MTC value decreases when the control rod is inserted into the active core while the FTC value increases. The total ppf results and temperature in steady-state rise when the control rods are inserted of into the active core whereby the maximum value occurs at the position of the control rods of 20 cm from the bottom of the active core. The calculation results of ppf, reactivity coefficient, and thermal-hydraulics parameters lay below safety limits, indicating that the TRIGA 2000 reactor can safely use U 3 Si 2 -Al silicide fuel as a substitute fuel for cylindrical type fuel. ABSTRAK ANALISIS NEUTRONIK DAN TERMOHIDRAULIK PENGARUH POSISI BATANG KENDALI TERHADAP KESELAMATAN OPERASI REAKTOR TRIGA 2000. Analisis parameterneutronikdan termohidraulik dari seluruh siklus operasi sangat penting untuk keselamatan operasi reaktor. Selama siklus operasi reaktor, posisi batang kendali akan berubah karena perubahan reaktivitas. Tujuan dari penelitian ini adalah untuk mengetahui pengaruh posisi batang kendali terhadap parameter neutronik dan termohidraulik terkait keselamatan operasi reaktor TRIGA 2000 menggunakan bahan bakar silisida jenis MTR. Parameter yang ditentukan adalah faktor puncak daya, koefisien reaktivitas, dan parameter termohidraulika pada keadaan tunak. Perhitungan neutronikl dilakukan menggunakan kombinasi program WIMSD/5 dan Batan-3DIFF dan untuk termohidraulik dilakukan menggunakan program WIMSD/5 dan MTRDYN. Hasil perhitungan menunjukkan bahwa nilai koefisien reaktivitas negatif untuk semua posisi batang kendali baik pada kondisi CZP dan HFP. Nilai MTC berkurang ketika batang kendali dimasukkan ke teras aktif sementara nilai FTC meningkat. Hasil ppf total dan parameter dalam kondisi tunak meningkat dengan memasukkan batang kendali ke dalam teras aktif dimana nilai maksimum terjadi pada posisi batang kendali 20 cm dari bagian bawah teras aktif. Hasil perhitungan ppf, koefisien reaktivitas dan parameter termohidraulik berada di bawah batas keselamatan, ini menunjukkan bahwa reaktor TRIGA 2000 dapat menggu...

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Core conversion design study of TRIGA Mark 2000 Bandung using MTR plate type fuel element

Cited by 19 publications

References 0 publications

Analysis on the Performance of the Bandung Conversion Fuel-Plate Triga Reactor in Steady State With Constant Coolant Flow Rate

Analysis on the Performance of the Bandung Conversion Fuel-Plate Triga Reactor in Steady State With Constant Coolant Flow Rate

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

Neutronic and Thermal Hydraulics Analysis of Control Rod Effect on the Operation Safety of Triga 2000 Reactor

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