Calculation of LEU Fuel Burn-up and Core Life Time Estimation of BAEC TRIGA Research Reactor Using 2D-TRIGLAV Code

Abstract

The BAEC TRIGA research reactor's (BTRR) core lifetime measurement and burn-up calculation were both carried out using the deterministic computation analysis tool TRIGLAV. Since it reached its first criticality in 1986, the BTRR has been used for nuclear research, instruction, training, and the manufacture of radionuclides for around 815 megawatt days without any core reloading or fuel reshuffling. The individual and ring-by-ring fuel burn-up and the core excess reactivity of BTRR have been studied utilizing the TRIGLAV code. The calculated outcomes of the TRIGLAV code and the outcomes of the MVP-BURN code are contrasted. To validate the TRIGLAV code for BTRR core analysis, the initial criticality and operational core analysis metrics like effective multiplication factor and excess reactivity were calculated using the TRIGLAV code. The results from TRIGLAV were compared with experimental data and other codes' output data and showed excellent agreement between them. Actual operational data is contrasted with core excess reactivity data. While the core excess reactivity data will forecast the core life, the collected fuel burn-up information can be used to forecast the core life. The collected fuel burn-up data can be utilized to reload or reorder the fuel. The BTRR may be used safely for an additional 500 MWD by the burn-up and excess reactivity requirements, according to the calculated fuel burn-up, identification of the hottest fuel rod, and excess reactivity value.