The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor
Abstract
Keywords
Full Text:
PDFReferences
(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
Refbacks
- There are currently no refbacks.
Published by INSIGHT - Indonesian Society for Knowledge and Human Development