Analyzing Simplified BWR Inherent Safety System using IAEA Generic Boiling Water Reactor Simulator
DOI:
https://doi.org/10.26740/jpfa.v11n2.p114-126Keywords:
Boiling water reactor, Inherent safety, Loss of coolant accident, IAEA simulatorAbstract
The inherent safety of boiling water reactors (BWR) has been a vital research topic in the past decades. This study aimed to observe and analyze the simplified BWR inherent safety system incorporated in IAEA Generic BWR Simulator. This simulator represents important features of BWR and provides graphical information and real-time simulation data. The simulated BWR has 1300 MWe power with ABWR-type containment. To analyze its inherent safety system, three conditions are simulated, i.e., normal condition at 100% power, transient condition (feedwater pumps trip), and emergency condition (loss of coolant accident—LOCA). The simulations were performed for up to 30 minutes since the most critical events in all conditions occurred within that time frame. Sequences of transient and emergency conditions were described in detail with the help of an additional screen recorder and time counting software. Results of several parameters in all simulation conditions were compared and analyzed. It was concluded that the simulator could simulate the normal, transient, and emergency conditions and the simplified version of the BWR inherent safety system.
References
International Energy Agency. Electricity Information: Overview. 2020. Available from: https://www.iea.org/reports/electricity-information-overview.
International Atomic Energy Agency. Reference Data Series No. 2: Nuclear Power Reactors in the World; 2019. Available from: https://www-pub.iaea.org/MTCD/Publications/PDF/RDS-2-39_web.pdf.
Strupczewski A. Accident Risks in Nuclear-Power Plants. Applied Energy. 2003; 75(1–2): 79–86. DOI: https://doi.org/10.1016/S0306-2619(03)00021-7.
Hansson SO. Promoting Inherent Safety. Process Safety and Environmental Protection. 2010; 88(3): 168–172. DOI: https://doi.org/10.1016/j.psep.2010.02.003.
Orlov VV, Avrorin EN, Adamov EO, Vasil’ev AP, Velikhov EP, Vertmna AA, Gorynon IV, Gromov BF, Zvezdin YI, Ignatov VA, Slesarev IS, Solonin MI, Subbotin VI, and Khromov VV. Nontraditional Concepts of Nuclear Power Plants with Inherent Safety (New Nuclear Technology for the next Stage of Large-Scale Production of Nuclear Power). Atomic Energy. 1992; 72(4): 287–296. DOI: https://doi.org/10.1007/BF00760874.
Forsberg CW. Boiling Water Neutronic Reactor Incorporating a Process Inherent Safety Design. 1985. Available from: https://www.osti.gov/doepatents/biblio/5053870-boiling-water-neutronic-reactor-incorporating-process-inherent-safety-design.
Forsberg CW. A Process Inherent Ultimate Safety Boiling Water Reactor. Nuclear Technology. 1986; 72(2): 121–134. DOI: https://doi.org/10.13182/NT86-A33735.
Mizuno T, Ito T, and Ohta K. The Inherently-Safe Fluidized-Bed Boiling Water Reactor Concept. Annals of Nuclear Energy. 1990; 17(9): 487–492. DOI: https://doi.org/10.1016/0306-4549(90)90003-V.
Wulff W, Cheng HS, Lekach SV, Stritar A, and Mallen AN. Development of BWR Plant Analyzer, in: Twelfth Water Reactor Safety Research Information Meeting. Maryland: US Nuclear Regulatory Commission;1984: 431-434. Available from: https://www.nrc.gov/docs/ML0422/ML042240550.pdf.
Harrington RM and Fuller LC. BWR-LTAS: A Boiling Water Reactor Long-Term Accident Simulation Code. International Nuclear Information System. 1985; 16(18): 16064715. Available from: http://inis.iaea.org/search/search.aspx?orig_q=RN:16064715.
Smith KS. BWR [Boiling Water Reactor] Shutdown Margin Model in SIMULATE-3. Transactions of the American Nuclear Society. 1990; 61: 369–371. Available from: http://inis.iaea.org/search/search.aspx?orig_q=RN:22044077.
Aybar HS and Aldemir T. Simulator Development for the Ohio State University Inherently Safe Reactor Using the DSNP Language. Mathematical Methods and Supercomputing in Nuclear Application Proceedings. 1993; 1: 878. Available from: http://inis.iaea.org/search/search.aspx?orig_q=RN:25062197.
Ivanov K, Olson A and Sartori E. OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes. Nuclear Science and Engineering. 2004; 148(2): 195–207. DOI: https://doi.org/10.13182/NSE04-A2451.
International Atomic Energy Agency. Boiling Water Reactor Simulator: Workshop Material. Vienna: IAEA; 2005. Available from: https://www-pub.iaea.org/MTCD/Publications/PDF/TCS-23_2nd_web.pdf.
Walhikmah R and Mahmudah RSN. Parameter Analysis of Triga Research Reactor with PCTRAN Pool Reactor Simulator. 2020 Annual Nuclear Safety Seminar Proceeding, Jakarta: BAPETEN. 2020: 31-39. Available from: https://bapeten.go.id/upload/15/19f13a9da7-prosiding-skn-2020.pdf.
U. T. T. Center. Reactor Concept Manual: Boiling Water Reactor (BWR) System. Washington: USNRC; 2012.
IAEA. Boiling Water Reactor Simulator with Active Safety System User Manual. Vienna: IAEA; 2011.
Muto S, Yokomizo O, Yoshimoto Y, Fukahori T, and Ebata S. Space-Dependent Analysis of BWR Core Nuclear Thermal Hydraulic Instability and Thermal Margin. Nuclear Engineering and Design. 1990; 120(2–3): 227–239. DOI: https://doi.org/10.1016/0029-5493(90)90375-8.
Choppin G, Liljenzin J-O, Rydberg J and Ekberg C. Chapter 20 - Nuclear Power Reactors, in: Radiochemistry and Nuclear Chemistry (Fourth Edition). Oxford: Academic Press; 2013: 655–684. DOI: https://doi.org/10.1016/B978-0-12-405897-2.00020-3.
Pandey V and Singh S. Characterization of Stability Limits of Ledinegg Instability and Density Wave Oscillations for Two-Phase Flow in Natural Circulation Loops. Chemical Engineering Science. 2017; 168: 204–224. DOI: https://doi.org/10.1016/j.ces.2017.04.041.
Boure JA, Bergles AE and Tong LS. Review of Two-Phase Flow Instability. Nuclear Engineering and Design. 1973; 25(2): 165–192. DOI: https://doi.org/10.1016/0029-5493(73)90043-5.
Rizwan-Uddin. On Density-Wave Oscillations in Two-Phase Flows. International Journal of Multiphase Flow. 1994; 20(4): 721–737. DOI: https://doi.org/10.1016/0301-9322(94)90041-8.
Paul S and Singh S. On Nonlinear Dynamics of Density Wave Oscillations in a Channel with Non-Uniform Axial Heating. International Journal of Thermal Sciences. 2017; 116: 172–198. DOI: https://doi.org/10.1016/j.ijthermalsci.2017.02.008.
Suwoto, Zuhair and Rivai AK. Simulasi Penurunan Level Daya Reaktor dengan Simulator BWR. Prosiding Seminar Nasional ke-8 Teknologi dan Keselamatan PLTN serta Fasilitas Nuklir. Jakarta: Center for Development of Advanced Reactor System, National Atomic Energy Agency; 2002. Available from: https://www.osti.gov/etdeweb/servlets/purl/20788523.
Shi S, Schlegel JP, Brooks CS, Lin YC, Eoh J, Liu Z, Zhu Q, Liu Y, Hibiki T, and Ishii M. Experimental Investigation of Natural Circulation Instability in a BWR-Type Small Modular Reactor. Progress in Nuclear Energy. 2015; 85: 96–107. DOI: https://doi.org/10.1016/j.pnucene.2015.06.014.
Ewing SM, Johnson N, and Sabharwall P. Quantification of Functional Impact Classification on The Current US Nuclear Fleet. 2017 ANS Annual Meeting. US: Idaho National Laboratory; 2017. Available from: https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_1169.pdf.
Wang TY, Hsu YT, Chen SW, Wang JR, Shih CK, Chiang SC, and Yu TY. The Analysis of Effectiveness of BWR/6 URG Strategies. Applied Mechanics and Materials. 2017; 865: 701–706. DOI: https://doi.org/10.4028/www.scientific.net/AMM.865.701.
Valinčius M, Kaliatka T, Kaliatka A, and Ušpuras E. Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor. Science and Technology of Nuclear Installations. 2018; 2018: 7162387. DOI: https://doi.org/10.1155/2018/7162387.
Ortiz-Villafuerte J, Viais-Juárez J, Araiza-Martiez E, and Amador-García R. BWR Mark II LOCA DBA Severe Accident Simulation with RELAP/SCDAPSIM. IAEA Tecdoc Series. 2019; 170-183. Available from: https://inis.iaea.org/collection/NCLCollectionStore/_Public/50/075/50075227.pdf?r=1.
Gauntt R. Severe Accident Phenomena Part 1: In-Vessel. IAEA Workshop on Severe Accident Management Guidelines. Austria: IAEA; 2017. Available from: https://inis.iaea.org/collection/NCLCollectionStore/_Public/49/066/49066570.pdf.
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