Determining Coolant Flow Rate Distribution In The Fuel-Modified TRIGA Plate Reactor

Hastuti, Endiah Puji; Widodo, Surip; Isnaini, M. Darwis; Rina, S. Geni; Bakhri, Syaiful

doi:10.1088/1742-6596/962/1/012045

Cited by 8 publications

(8 citation statements)

References 8 publications

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“…The minimum flow rate of the primary cooling system is 70 kg/s and about 85% of the total flow rate or 59.5 kg/s flow cools the reactor core [16]. In this context, the term active flow rate is defined as a flow that is directly in contact with the fuel element plate.…”

Section: Methodsmentioning

confidence: 99%

“…This accident provides a positive reactivity, and as a result, the power will rise quickly until the reactor scrams. The trip signal that causes a flux-trap reactor comes from a too high neutron flux (overpower 118 % nominal power) with a delay time of 0.5 s and the control rod time to below 0.5 s. The calculation used coolant inlet temperature of 35 o C and a pressure of 1.8 MPa [16].…”

Section: Methodsmentioning

confidence: 99%

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Safety Analysis of the TRIGA 2000 U3Si2-Al Fuel Core Under Reactivity Insertion Accidents

2020

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The TRIGA 2000 reactor in Bandung is planned to change its fuel type from the TRIGA fuel rod type to the U 3 Si 2-Al plate type of low enriched uranium of 19.75 % with uranium density of 2.96 gU/cc. A study on the neutronic parameters from the equilibrium core has been done. To ensure safe operation of the new fuel, thermodynamic evaluation of the core needs to be done. The purpose of this study is to conduct a reactor safety analysis of reactivity insertion during withdrawal of the control rod and to study the effect of this reactivity insertion on the power and the maximum temperature of the fuel and the cladding. Reactivity insertion accident is the main factor of the design basis accidents in nuclear reactor design. A simulation of transient for reactivity insertion has been carried out using a coupled neutronic and thermal-hydraulic MTR-DYN code. The code was developed based on threedimensional multigroup neutron diffusion theory. The coupled space and timedependent problem were solved by adiabatic model. Transient analysis was performed for a reactivity insertion of 32.33 pcm/s with the assumption that all of the control rods were rapidly withdrawn. For the insertion at a low power of 100 W, the maximum power achieved was 2.74 MW while a maximum power of 2.3 MW was achieved for the power transient of 1 MW. The maximum temperature of the coolant, the cladding, and the fuel for TRIGA 2000 core does not exceed the allowable safety limit for reactivity insertions.

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Section: Methodsmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

Safety Analysis of the TRIGA 2000 U3Si2-Al Fuel Core Under Reactivity Insertion Accidents

2020

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“…The minimum flow rate of the primary cooling system is 70 kg/s and only 59.5 kg/s cools the reactor core. The core inlet temperature of 35 o Cand a pressure of 1.8 Mpa [16].…”

Section: Thermal Hydraulic Parameter Calculationmentioning

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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“…Subekti et al have performed analysis of coolant velocity in plate-type fuel element using CFD method for RSG-GAS [10]. Meanwhile, Endiah et al also have carried out an analysis on flow rate distribution in the plate-type TRIGA reactor core using Caudvap code, of which one of the results is that the coolant flow rate through the fuel plate is 88.2% [11].…”

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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Determining Coolant Flow Rate Distribution In The Fuel-Modified TRIGA Plate Reactor

Cited by 8 publications

References 8 publications

Safety Analysis of the TRIGA 2000 U3Si2-Al Fuel Core Under Reactivity Insertion Accidents

Safety Analysis of the TRIGA 2000 U3Si2-Al Fuel Core Under Reactivity Insertion Accidents

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

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

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