Thermal-hydraulic analysis of fuel rod of a TRIGA Mark II research reactor

 
 
 
  • Abstract
  • Keywords
  • References
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  • Abstract


    In this work, the feasibility of employing “Single Flow Channel Analysis” technique for obtaining the thermal-hydraulic behavior of a TRIGA Mark II research reactor has been studied. Two different simulation methods have been investigated for this purpose; one in which there is no variation in volumetric heat generation along the fuel axis and the other in which there is variation. A hot rod factor of 1.70 has been taken. Results obtained from simulation methods have been compared with both theoretical results and experimental data provided by the manufacturers. Results show that data generated from both simulation methods are more accurate compared to theoretical calculations. Also, the simulation method exempting variation of heat generation has predicted maximum temperature of the fuel centerline just above 750 oC, which is sufficiently accurate. However, temperatures obtained at different axial and radial locations are not close to the experimental values. On the other hand, the simulation technique in which variation of heat generation exists has been able to provide temperature profiles inside the fuel rod and cladding surface almost identical to the experimental values. However, temperature profile of the fuel outer surface is found to be quite different from experimental values.

     

     


  • Keywords


    Hot Rod Factor; Research Reactor; Temperature Distribution; Thermal-Hydraulics.

  • References


      [1] Anglart H. Applied Reactor Technology. 2011.

      [2] Glaser A. About the enrichment limit for research reactor conversion: Why 20%? In: International Meeting on Reduced Enrichment for Research and Test Reactors (hereinafter referred to as RERTR conference), Boston 2005 Nov 6.

      [3] TRIGA Power System: A Passive Safe Co-Generation Unit for Electric Power and Low Temperature Heat, Small Reactors for Low Temperature Heat Applications, IAEA-TECDOC-463 (International Atomic Energy Agency, Vienna, 1988) pp. 45-55.

      [4] Yamanaka S, Yamada K, Kurosaki K, Uno M, Takeda K, Anada H, Matsuda T, Kobayashi S. Thermal properties of zirconium hydride. Journal of Nuclear Materials. 2001;294(1-2):94-8. https://doi.org/10.1016/S0022-3115(01)00457-3.

      [5] Toma C, Parvan M, Tuturici IL. Characterization of TRIGA LEU fuel behavior, irradiated in 14 MW core. 2002.

      [6] Olander DR, Ng M. Hydride fuel behavior in LWRs. Journal of nuclear materials. 2005;346(2-3):98-108. https://doi.org/10.1016/j.jnucmat.2005.05.017.

      [7] Wongsawaeng D, Olander D. Liquid-metal bond for LWR fuel rods. Nuclear Technology. 2007;159(3):279-91. https://doi.org/10.13182/NT07-A3876.

      [8] Olander D, Greenspan E, Garkisch HD, Petrovic B. Uranium–zirconium hydride fuel properties. Nuclear Engineering and Design. 2009;239(8):1406-24. https://doi.org/10.1016/j.nucengdes.2009.04.001.

      [9] Žerovnik G, Snoj L, Trkov A, Barbot L, Fourmentel D, Villard JF. Measurements of thermal power at the TRIGA Mark II reactor in Ljubljana using multiple detectors. IEEE Transactions on Nuclear Science. 2014;61(5):2527-31. https://doi.org/10.1109/TNS.2014.2356014.

      [10] Nacir B, Boulaich Y, Chakir E, El Bardouni T, El Bakkari B, El Younoussi C. Safety analysis and optimization of the core fuel reloading for the Moroccan TRIGA Mark-II reactor. Annals of Nuclear Energy. 2014; 70:312-6. https://doi.org/10.1016/j.anucene.2013.11.040.

      [11] Agbo SA, Ahmed YA, Ewa IO, Jibrin Y. Analysis of Nigeria research reactor-1 thermal power calibration methods. Nuclear Engineering and Technology. 2016;48(3):673-83. https://doi.org/10.1016/j.net.2016.01.014.

      [12] Štancar Ž, Snoj L. An improved thermal power calibration method at the TRIGA Mark II research reactor. Nuclear Engineering and Design. 2017; 325:78-89. https://doi.org/10.1016/j.nucengdes.2017.10.007.

      [13] Cammi A, Ponciroli R, di Tigliole AB, Magrotti G, Prata M, Chiesa D, Previtali E. A zero-dimensional model for simulation of TRIGA Mark II dynamic response. Progress in Nuclear Energy. 2013; 68:43-54. https://doi.org/10.1016/j.pnucene.2013.04.002.

      [14] El Bakkari B, El Bardouni T, Nacir B, El Younoussi C, Boulaich Y, Boukhal H, Zoubair M. Fuel burnup analysis for the Moroccan TRIGA research reactor. Annals of Nuclear Energy. 2013; 51:112-9. https://doi.org/10.1016/j.anucene.2012.07.030.

      [15] Türkmen M, Çolak Ü. Analysis of ITU TRIGA Mark II research reactor using Monte Carlo method. Progress in Nuclear Energy. 2014; 77:152-9. https://doi.org/10.1016/j.pnucene.2014.06.015.

      [16] Coban R. Power level control of the TRIGA Mark-II research reactor using the multifeedback layer neural network and the particle swarm optimization. Annals of Nuclear Energy. 2014; 69:260-6. https://doi.org/10.1016/j.anucene.2014.02.019.

      [17] Alloni D, di Tigliole AB, Cammi A, Chiesa D, Clemenza M, Magrotti G, Pattavina L, Pozzi S, Prata M, Previtali E, Salvini A. Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP. Progress in Nuclear Energy. 2014; 74:129-35. https://doi.org/10.1016/j.pnucene.2014.02.022.

      [18] Henry R, Tiselj I, Snoj L. Analysis of JSI TRIGA MARK II reactor physical parameters calculated with TRIPOLI and MCNP. Applied radiation and isotopes. 2015; 97:140-8. https://doi.org/10.1016/j.apradiso.2014.12.017.

      [19] Mghar M, Chetaine A, Darif A. Calculation of kinetic parameters of the Moroccan TRIGA Mark-II reactor using the Monte Carlo code MCNP. Advances in Applied Physics. 2015;3(1):1-8. https://doi.org/10.12988/aap.2015.531.

      [20] Cammi A, Zanetti M, Chiesa D, Clemenza M, Pozzi S, Previtali E, Sisti M, Magrotti G, Prata M, Salvini A. Characterization of the TRIGA Mark II reactor full-power steady state. Nuclear Engineering and Design. 2016; 300:308-21. https://doi.org/10.1016/j.nucengdes.2016.01.026.

      [21] Ćalić D, Žerovnik G, Trkov A, Snoj L. Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments. Applied Radiation and Isotopes. 2016; 107:165-70. https://doi.org/10.1016/j.apradiso.2015.10.022.

      [22] Henry R, Tiselj I, Snoj L. CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor. Annals of Nuclear Energy. 2017; 110:36-47. https://doi.org/10.1016/j.anucene.2017.06.018.

      [23] Manual for Description of the BAEC TRIGA Research Reactor. Bangladesh Atomic Energy Commission, 2012.

      [24] Lyric ZI, Mahmood MS, Motalab MA, Khan JH. Optimum burnup of BAEC TRIGA research reactor. Annals of Nuclear Energy. 2013; 55:225-9. https://doi.org/10.1016/j.anucene.2012.12.019.

      [25] Khan MJ, Sarker MM, Islam SM. Analysis of kinetic parameters of 3 MW TRIGA Mark-II research reactor using the SRAC2006 code system. Annals of Nuclear Energy. 2013; 60:181-6. https://doi.org/10.1016/j.anucene.2013.05.009.

      [26] Salam MA, Soner MA, Sarder MA, Haque A, Uddin MM, Sarker MM, Islam SM. Measurement of control rod reactivity and shut down margin of 3 MW TRIGA Mark-II research reactor using analogue and digital I&C system. Annals of Nuclear Energy. 2014; 68:257-61. https://doi.org/10.1016/j.anucene.2014.01.030.

      [27] Rahman MM, Akond MA, Basher MK, Huda MQ. Steady-state thermal-hydraulic analysis of TRIGA research reactor. World Journal of Nuclear Science and Technology. 2014;4(02):81. https://doi.org/10.4236/wjnst.2014.42013.

      [28] Salam MA, Soner MA, Sarder MA, Haque A, Uddin MM, Rahman A, Rahman MM, Sarkar MM, Islam SM. Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor. Progress in Nuclear Energy. 2014; 74:160-5. https://doi.org/10.1016/j.pnucene.2014.02.025.

      [29] Hosan MI, Soner MA, Kabir KA, Salam MA, Huq MF. Study on neutronic safety parameters of BAEC TRIGA research reactor. Annals of Nuclear Energy. 2015; 80:447-50. https://doi.org/10.1016/j.anucene.2015.02.031.

      [30] Hoq MA, Soner MM, Rahman A, Salam MA, Islam SM. Estimation of 41Ar activity concentration and release rate from the TRIGA Mark-II research reactor. Journal of environmental radioactivity. 2016; 153:68-72. https://doi.org/10.1016/j.jenvrad.2015.12.005.

      [31] 3MW TRIGA-Mark-II Research Reactor’s Safety Analysis Report, Bangladesh Atomic Energy Commission, 1986, General Atomics, USA.

      [32] Thermal properties of metals, metallic elements and alloys. Available online: https://www.engineeringtoolbox.com/thermal-conductivity-metals-d_858.html.


 

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Article ID: 30035
 
DOI: 10.14419/ijet.v9i1.30035




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