INVESTIGASI KARAKTERISTIK TERMOHIDROLIKA TERAS REAKTOR DAYA KECIL DENGAN PENDINGINAN SIRKULASI ALAM MENGGUNAKAN RELAP5
DOI:
https://doi.org/10.17146/tdm.2016.18.1.2330Keywords:
small modular reaktor, PWR, natural circulation, RELAP5, thermal-hydraulicAbstract
INVESTIGATION ON CORE THERMAL HYDRAULIC CHARACTERISTICS OF SMALL MODULAR REACTOR WITH NATURAL CIRCULATION COOLING USING RELAP5. Small modular reactor (SMR ) is very prospective to be deployed in Indonesia. Its low output power, compact design and capability to be constructed modularly provide better deployment flexibility compared to a large conventional reactor. There are various designs of SMRs, one of them implements natural circulation for its primary cooling system or in other words the reactor uses no primary pumps. Besides, the dimension of fuel element is shorter than the one used by large reactor. These two aspects may produce different heat transfer behavior, which could lead to a safety implication. For that reason, this research investigates thermal hydraulic characteristics of the core of SMR with naturally circulating coolant, especially on the fuel and coolant temperatures and mass flow rate. The purpose is to identify the thermal safety margin difference of the reactor compared with conventional PWR. The investigation was performed using RELAP5 in which the core was partially represented by means of generic models of the program and continued with steady state calculations. The result shows that during nominal power operation, the reactor has better of 2K degree for boiling temperature margin than the large conventional PWR. In addition, the excellence of SMR safety margin was shown by the increase of primary coolant flow rate following the increase of power, which means that the reactor has a distinctive inherent safety.
References
Hidayatullah, H., S. Susyadi, and M.H. Subki, Design and Technology Development for Small Modular Reactors - Safety Expectations, Prospects and Impediments of Their Deployment. Progress in Nuclear Energy, 2015. 79(0): p. 127-135.
https://doi.org/10.1016/j.pnucene.2014.11.010
Sullivan, M.A., et al., The Future of Nuclear Power. The Electricity Journal, 2014. 27(4): p. 7-15.
https://doi.org/10.1016/j.tej.2014.04.008
Kessides, I.N. and V. Kuznetsov, Small Modular Reactors for Enhancing Energy Security in Developing Countries, 2012, World Bank: Washington DC, USA. p. 26 pp.
https://doi.org/10.3390/su4081806
Schulz, T.L., Westinghouse AP1000 advanced passive plant. Nuclear Engineering and Design, 2006. 236(14-16): p. 1547-1557.
https://doi.org/10.1016/j.nucengdes.2006.03.049
Agrawal, S.K., A. Chauhan, and A. Mishra, The VVERs at KudanKulam. Nuclear Engineering and Design, 2006. 236(7-8): p. 812-835.
https://doi.org/10.1016/j.nucengdes.2005.09.030
Nguyen, T., et al., Development of severe accident management guidance (SAMG) for the Canadian CANDU 6 nuclear power plants. Nuclear Engineering and Design, 2008. 238(4): p. 1093-1099.
https://doi.org/10.1016/j.nucengdes.2007.08.005
Lumbanraja, S.M., Kajian Implementasi FLEXBLUE di Indonesia. Jurnal Pengembangan Energi Nuklir V, 2014. 16(2): p. 107 - 117.
Carelli, M.D., et al., The design and safety features of the IRIS reactor. Nuclear Engineering and Design, 2004. 230(1-3): p. 151-167.
https://doi.org/10.1016/j.nucengdes.2003.11.022
Halfinger, J.A. and M.D. Haggerty, The B&W mPOWER Scalable Practical Nuclear Reactor Design. Nuclear Technology, 2012. 178(May 2012): p. 164-169.
https://doi.org/10.13182/NT11-65
Ingersoll, D.T., Deliberately small reactors and the second nuclear era. Progress in Nuclear Energy, 2009. 51(4-5): p. 589-603.
https://doi.org/10.1016/j.pnucene.2009.01.003
Fukami, M.V.I. and A. Santecchia, CAREM project: Innovative small PWR. Progress in Nuclear Energy, 2000. 37(1-4): p. 265-270.
https://doi.org/10.1016/S0149-1970(00)00057-3
José N. Reyes, J., NuScale Plant Safety in Response to Extreme Events. Nuclear Technology, 2012. 178(128): p. 153-163
https://doi.org/10.13182/NT12-A13556
Marcel, C.P., et al., Stability of self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The stability performance of the CAREM-25 reactor. Nuclear Engineering and Design, 2013. 265(0): p. 232-243.
https://doi.org/10.1016/j.nucengdes.2013.08.057
Reyes Jr, J.N. and P. Lorenzini, NuScale Power: A modular, scalable approach to commercial nuclear power. Nuclear News, 2010. 53(7): p. 97.
Ingersoll, D.T., et al., NuScale small modular reactor for Co-generation of electricity and water. Desalination, 2014. 340(0): p. 84-93.
https://doi.org/10.1016/j.desal.2014.02.023
José N. Reyes, J., Introduction to NuScale Design, in U.S. Nuclear Regulatory Commission Pre-Application Meeting2008, NuScale Power Inc.: Rockville, MD.
Jose N. Reyes, J. Meeting Introduction and Overview of NuScale Design. in U.S. Nuclear Regulatory Commission Pre-Application Meeting. 2009. Rockville, MD: NuScale Power.
NuScale. NuScale Status in the Regulatory Process. 15 June 2015]; Available from: http://www.nuscalepower.com/our-technology/nrc-interaction.
Song, K.-n. and S.-h. Lee, Effect of Weld Properties on the Crush Strength of the PWR Spacer Grid. Science and Technology of Nuclear Installations, 2012. 2012: p. 12.
https://doi.org/10.1155/2012/540285
Modro, S., et al., Multi-application small light water reactor final report. Idaho National Engineering and Environmental Laboratory, 2003.
https://doi.org/10.2172/839135
Sutharshan, B., et al., The AP1000TM Reactor: Passive Safety and Modular Design. Energy Procedia, 2011. 7(0): p. 293-302.
