The Thermohydraulic Analysis of the Bandung Research Reactor Core With Plate Type Fuel Elements Using the CFD Code

Nazar, Reinaldy; Ka, Sudjatmi; Kamajaya, Ketut

doi:10.17146/tdm.2018.20.3.4626

Cited by 4 publications

(4 citation statements)

References 3 publications

(3 reference statements)

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“…The core configuration is shown in Figure 3 and the neutronic parameters are shown in Table 1. If the reactor power is 2 MW, the minimum flow to the reactor core is 70 kg/s [20] and for nominal power of 1 MW, the minimum flow rate of 50 kg/s is needed.…”

Section: Methodology Triga Mark 2000 Reactor Descriptionmentioning

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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Section: Methodology Triga Mark 2000 Reactor Descriptionmentioning

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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“…The TRIGA 2000 has two pri mary cool ing pumps for re mov ing the heat from the pri mary cool ant sys tem to the sec ond ary cool ant sys tem [17,18]. In con vert ing the re ac tor core, a nat u ral cir cu la tion flap will be in stalled in the core cool ing sys tem.…”

Section: Re Ac Tor Core De Scrip Tionmentioning

confidence: 99%

Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes

2021

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The TRIGA 2000 reactor Bandung is proposed to convert from rod-type fuel to plate-type fuel because there are no manufacturers in the world that still produce rod-type fuel. Calculating the safety parameters and their reliability related to reactor operation has become an important thing to do. The objective of this study was to perform the reactor transient calculation of TRIGA 2000 that uses plate-type fuel. The reactor core modification is based on the capability of the existing primary coolant system, without changing its flow rates. Thermal-hydraulics calculations related to reactivity insertion accident and loss of flow accident were analyzed using EUREKA2/RR, MTR-DYN, and RELAP5 codes. The chosen loss of flow accident scenario is a decrease in flow caused by a sudden stop of the pump power supply, while reactivity insertion accident is conducted by the withdrawal of control rods with maximum reactivity insertion of 32.33 ? 10?5 s?1. The calculated parameters are reactivity, reactor power, and temperature of the coolant, cladding, and fuel in the hottest channel position. In general, from a safety point of view, those computer codes were capable of performing the transient calculations with appropriate results. Based on the calculation results, during the transient condition of both reactivity insertion accident and loss of flow accident scenario, the reactor operation safety parameters do not exceed the allowable safety limit.

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“…The inherent safety calculation is performed on the operating conditions cold zero power (CZP) and hot full power (HFP). Thermodynamic parameters due to the effect of the control rod position in the design of research reactors the MTR type is very important for safe operation and optimization of the fuel used [8,9].This data is needed for the preparation of the safety analysis report (SAR) for the conversion of fuel from the cylinder type to the MTR type.…”

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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The Thermohydraulic Analysis of the Bandung Research Reactor Core With Plate Type Fuel Elements Using the CFD Code

Cited by 4 publications

References 3 publications

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

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

Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes

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

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