Thermal Hydraulics Safety Analysis at Steady State Operation of Burnup Core of TRIGA Mark II Research Reactor Utilizing PARET/ANL and COOLOD-N2

Yıl 2024, Cilt: 37 Sayı: 2, 41 - 45, 09.01.2025

Md Altaf Hossen

Öz

Steady-state thermal hydraulics analysis of 700 MWD burn core of the TRIGA Mark II research reactor has been studied with the computational codes PARET/ANL and COOLOD-N2. This study aims to validate the PARET/ANL code through the execution of steady-state thermal-hydraulics calculations at full power to guarantee that all safety parameters maintain margins well below the safety limits. Fuel centerline temperature, Fuel surface temperature, Fuel clad temperature, DNB heat flux, and DNB ratio of the hottest rod, Enthalpy and Coolant temperature have been calculated. Results from both codes are in good agreement with each other which are far below the safety limit of SAR. Hence PARET/ANL is capable in conducting TRIGA mark II research reactor. Therefore, thermal hydrualics packages and correlations used in this simulation can be utilized for the thermal hydraulics safety analysis of modified TRIGA Mark II cores.

Anahtar Kelimeler

Thermal hydraulics, PARET/ANL, COOLOD-N2, Burn up

Kaynakça

• [1] Hossain, S. M., Zulquarnain, M. A., Kamal, I. and Islam, M.N. Current Status and Perspectives of Nuclear Reactor Based Research in Bangladesh, IAEA, Vienna, (2011), 7-14. IAEA-TECDOC-1659
• [2] Mizanur Rahman M. M., Akond M. A. R., Basher M K., and Huda M. Q., Steady State Thermal Hydraulic Analysis of TRIGA Research Reactor, World Journal of Nuclear Science and Technology, (2014), 81-87. DOI: 10.4236/wjnst.2014.42013
• [3] Huda M. Q. and Rahman M., Thermo-Hydrodynamic Design and Safety Parameter Studies of the TRIGA MARK II Research Reactor, Annals of Nuclear Energy, 31, (2004) 1101-1118. https://doi.org/10.1016/j. anucene.2004.02.001
• [4] Altaf M. H. and Badrun N. H., Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup, Atom Indonesia, 40 (2014) 107-112. DOI:10.17146/ aij.2014.328
• [5] Sudo, Y., Ikawa, H. and Kaminaga, M, Development of Heat Transfer Package for Core Thermal Hydraulics Design and Analysis of Upgradded JRR-3. Proceedings of the International Meeting of Reduced Enrichment for Research and Test Reactors, Petten, (1985) 363-372.
• [6] General Atomics, 10 MW TRIGA-LEU Fuel and Reactor Design Description. General Atomics, San Diego (1979).
• [7] Obenchain, C.F., PARET—A Program for the Analysis of Reactor Transients. IDO-17282, Idaho Atomic Energy, 1969.
• [8] Kaminaga, M., COOLOD-N2: A Computer Code, for the Analyses of Steady-State Thermal Hydraulics in Research Reactors, JAERI Report. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki, 1994.
• [9] Mahmood M. S. et al., Individual Fuel Element Burnup of BAEC TRIGA Core, Technical Report, INST-RPEDRARD- 01/009 (2012).
• [10] FSAR, Final Safety Analysis Report for 3 MW TRIGA MARK-II Research Reactor at AERE, Savar, Dhaka, Bangladesh. BAEC, Dhaka (2006).
• [11] Huda, M. Q., Bhuiyan, S. I., Chakroborty, T.K., Sarker, M.M. and Mondal, M.A.W. Thermal Hydraulic Analysis of the 3 MW TRIGA MARK-II Research”, Reactor. Nuclear Technology, 135, “(2001), 51-66. https://doi. org/10.13182/NT01-A3205.