ANALISIS DISTRIBUSI KECEPATAN PENDINGIN DALAM ELEMEN BAKAR TIPE PELAT MENGGUNAKAN METODE CFD UNTUK REAKTOR RISET RSG-GAS
Keywords:
Coolant flow, fuel element, research reactor, steady state, CFDAbstract
The measurement experiment for coolant-velocity distribution in the subchannel of fuel element of RSG-GAS research reactor is difficult to be carried out due to too narrow channel and subchannel placed inside the fuel element. Hence, the calculation is required to predict the coolant-velocity distribution inside subchannel to confirm that the handle presence does not ruin the velocity distribution into every subchannel. This calculation utilizes CFD method, which respect to 3-dimension interior. Moreover, the calculation of coolant-velocity distribution inside subchannel was not ever carried out. The research object is to investigate the distribution of coolant-velocity in plattyped fuel element using 3-dimention CFD method for RSG-GAS research reactor. This research is required as a part of the development of thermalhydraulic design of fuel element for innovative research reactor as well. The modeling uses ½ model in Gambit software and calculation uses turbulence equation in FLUENT 6.3 software. Calculation result of 3D coolant-velocity in subchannel using CFD method is lower about 4,06% than 1D calculation result due to 1D calculation obeys handle availability.
References
Pusat Reaktor Serba Guna (PRSG)-BATAN. Laporan Analisis Keselamatan RSG-GAS. Revisi 10. 2008.
Ha T., and Garland WJ. Hydraulic study of turbulence flow in MTR-Type nuclear fuel assembly. Journal of Nuclear Engineering and Design. 2006; 236: 975-984.
https://doi.org/10.1016/j.nucengdes.2005.10.004
Salam A., and El-Morshedy S. CFD simulation of The IAEA 10 MW Generic MTR reactor under loss of flow transient. Journal of Annal of Nuclear Engineering. 2011; 38: 564-577.
https://doi.org/10.1016/j.anucene.2010.09.025
Hamidouche T., et al. Dynamic calculation of the IAEA safety MTR research reactor benchmark problem using RELAP5/3.2 Code. Journal of Annal of Nuclear Engineering. 2004; 31: 1385-1402.
https://doi.org/10.1016/j.anucene.2004.03.008
Salam A. CFD investigation of flow inversion in typical MTR research reactor undergoing thermal-hydraulic transients. Journal of Annal of Nuclear Engineering. 2011; 38: 1578- 1592.
https://doi.org/10.1016/j.anucene.2011.03.005
Endiah PH., dan Subekti M. Analisis termohirolika elemen bakar uji U-7M0/Al dan U 6Zr/Al di RSG-GAS menggunakan COOLOD-N2, NATCON dan CFD-3D. Jurnal Ilmiah Daur Bahan Bakar Nuklir. 2013;19-1: 1-14.
Endiah PH., dkk. UCD reaktor riset inovatif. Dokumen Teknis Pusat Teknologi Reaktor dan Keselamatan Nuklir (PTRKN)-BATAN; 2010. No.: BATAN-RKN-06-2010.
International Nuclear Fual Cycle Evaluation (INFCE). Advanced fuel cycle and reactor concepts. report of working group 8; 1980. Report No.: INFCE/PC/2/8.
Isnaini MD., et al. Analisis distribusi laju alir desain teras reaktor riset inovatif berbahan bakar tingkat muat tinggi. Prosiding Seminar Nasional ke-18 Teknologi dan Keselamatan PLTN serta Fasilitas Nuklir (TKPFN-18). Bandung: 2012. hal. 97-108.