The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor

Andi S. Ekariansyah, Surip Widodo, - Sudarmono, - Susyadi, M. Darwis Isnaeni, R. Andika P. Dwijayanto

Abstract


Since 2014, Indonesia's National Atomic Energy Agency (BATAN) has been launching a plan to construct a 10 MWt Experimental Power Reactor (Reaktor Daya Eksperimental / RDE). The RDE design is based on the small-sized pebble-bed high-temperature gas-cooled reactor (HTGR) technology with TRISO fuels. By concept, HTR-10 design, which was developed by the INET of China, is used as the reference design. During the development process, a safety analysis report (SAR) of RDE design has to be prepared to be evaluated by the Indonesia Nuclear Regulatory Agency (BAPETEN). The report contains, among others the description of the RDE accident sequences, which can be only provided by simulations using a certain code. This paper emphasizes the transient analysis, which is simulated using RELAP5/SCDAP/Mod3.4 , which is a thermal-hydraulic code specified for light water coolant systems. The simulated event is the loss of primary coolant mass flow, which is caused by the failure of the primary gas blower motor. The methodology of simulation is first by modelling the RDE nuclear steam supply system to verify steady-state operational parameter of the RDE design. The second step is to simulate the event of loss of flow, which is followed by the failure to shut down the reactor. The simulation results in the decrease of the fuel pebble temperature during the event due to the negative fuel temperature reactivity coefficient and the core heat removal by the cavity cooling. Overall, the RELAP5 code has a limitation in the RDE simulation to define two different non-condensable gases, which reduces the accuracy of the simulation results.

Keywords


experimental power reactor; loss of flow; RELAP5; accident simulation.

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References


(2018) The World Nuclear News website. [Online]. Available: http:// http://www.world-nuclear-news.org/Articles/Progress-with-Indonesian-SMR-project

T. Taryo, G. R. Sunaryo, and M. Rachmawati, “The strategie to support HTGR fuels for the 10 MW Indonesia’s experimental power reactor (RDE)â€, Urania, vol. 24, pp. 1-72, Februari 2018.

Z. Zhang, Y. Dong, F. Li, Z. Zhang, H. Wang, X. Huang, H. Li, B. Liu, X. Wu, H. Wang, X. Diao, H. Zhang, and J. Wang, “The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) demonstration power plant: an engineering and technological innovationâ€, Engineering, vol. 2, pp. 112-118, March 2016

A. Kadak, “A future for nuclear energy: pebble bed reactorsâ€, Int. J. Critical Infrastructures, vol. 1, pp. 330-345, 2005.

Mudjiono, S. Alimah, D. Irawan, M. Busthomi, and H. Susiati, “Social engineering to the development plan of experimental power reactor (RDE)â€, in J. Phys.: Conf. Ser. 2019, paper 1198 022052

T. Setiadipura, Suwoto, Zuhair, “Equilibrium core design of Reaktor Daya Eksperimentalâ€, in J. Phys.: Conf. Ser. 2019, paper 1198 022076

T. M. Sembiring, P. A. Artiani, “Subcriticality analysis of HTR-10 spent fuel cask model for the 10 MW HTR Indonesian experimental power reactorâ€, J. Tek. Reaktor. Nukl., vol. 20, pp. 151-158, October 2018

C. M. Allison and J. K. Hohorst, “Project report: role of RELAP/SCDAPSIM in nuclear safetyâ€, Sci. Technol. Nucl. Ins, vol. 2010, Article ID 425658.

M. E. Scari, A. L. Costa, C. Pereira, C. E. Velasquez, M. A. F. Veloso, “HTR steady state and transient thermal analysesâ€, Int. J. Hydrog. Energy, vol. 41, pp. 7192-7196, March 2016.

A.S. Ekariansyah, M. Subekti, S. Widodo, H. Tjahjono, Susyadi, P.I. Wahyono, A. Budianto, “Development of experimental power reactor (EPR) model for safety analysis using RELAP5â€, J. Tek. Reaktor. Nukl., vol. 21, pp. 51-58, June 2019.

International Atomic Energy Agency, “Evaluation of high temperature gas cooled reactor performance: benchmark analysis related to the PBMR-400, PBMM, GT-MHR, HTR-10 and the ASTRA critical facilityâ€, Tec. Doc. 1694, 2013.

F. Chen, Y. Dong, Y. Zheng, L. Shi, and Z. Zhang, “Benchmark calculation for the steady-state temperature distribution of the HTR-10 under full-power operationâ€, J. Nucl. Sci. Technol., vol. 46, pp. 572-580, Februari 2009.

Z. Gao and L. Shi, “Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium coreâ€, Nucl. Eng. Des., vol. 218, pp. 51-64, March 2002.

S. Yamoah, E. H. K. Akaho, N. G.A. Ayensu, and M. Asamoah, “Analysis of fluid flow and heat transfer model for the pebble bed high temperature gas cooled reactorâ€, Res. J. App. Sci. Eng. Tech., vol. 4, pp. 1659-1666, June 2012.

H. Zhang, L. Zou, D. Andrs, H. Zhao and R. Martineau, “Point kinetics calculations with fully coupled thermal fluids reactivity feedbackâ€, in Int. Conf. M&C 2013, 2013.

M. Q. Huda, and T. Obara, “Development and testing of analytical models for the pebble bed type HTRsâ€, Ann. Nucl. Energy, vol. 35, pp. 1994-2005, August 2008.

M. Ilyas and F. Aydogan, “Steam generator performance improvements for integral small modular reactorsâ€, Nucl. Eng. Technol.,vol. 49, pp. 1669-1679, August 2017.

G. Zuying and S. Lei, “Thermal hydraulic transient analysis of the HTR-10â€, Nucl. Eng. Des., vol 218, pp. 65-80, March 2002.




DOI: http://dx.doi.org/10.18517/ijaseit.10.5.10817

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