RIA Analysis of Unprotected TRIGA Reactor

Altaf, M.H.; Islam, Shammunul; Badrun, N.H.

doi:10.17146/aij.2017.568

Cited by 3 publications

(3 citation statements)

References 2 publications

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“…The danger of RIA is that it can damage the integrity of the fuel because the level of fission in the reactor core increases, and it increases the reactor power to an undesired power level. The reactivity insertion accidents (RIA) under controlled and uncontrolled conditions have been investigated by several researchers [12][13][14]. RIA under control has been carried out to determine the safety of reactor operations [15].…”

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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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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“…Reactivity initiated transient analysis of TRIGA reactor is certainly not new although most of these works reported so far in the context of analysis fresh core [6][7][8]. But, in order to strengthening safety analysis, transient study with the progress of core burnt of unprotected TRIGA needs to be addressed which have not been conducted for TRIGA until to date.…”

Section: Introduction mentioning

confidence: 99%

Reactivity Initiated Transient Response of TRIGA with the Progress of Core Burnt

Haque¹,

Badrun

2020

Atom Indo.

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“…Excessive insertion of reactivity can cause accidents leading to fuel clad meltdown. In the past, many researchers conducted analysis on the reactivity insertion accidents (RIA) under controlled and un-controlled conditions, and they compiled the results in safety analysis reports [9][10][11][12].…”

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confidence: 99%

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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RIA Analysis of Unprotected TRIGA Reactor

Cited by 3 publications

References 2 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

Reactivity Initiated Transient Response of TRIGA with the Progress of Core Burnt

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

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