PERFORMANCE ANALYSIS OF RDE ENERGY CONVERSION SYSTEM IN VARIOUS REACTOR POWER CONDITION

Ignatius Djoko Irianto, Sukmanto Dibyo, Sriyono Sriyono, Djati H Salimy, Rahayu Kusumastuti, Marliyadi Pancoko

DOI: http://dx.doi.org/10.17146/tdm.2019.21.3.5570

Abstract


Reaktor Daya Eksperimental (RDE) is an experimental power reactor based on High Temperature Gas-cooled Reactor (HTGR) technology with thermal power of 10 MW. As an experimental power reactor, RDE is designed for electricity generation and provides thermal energy for experimental purposes. RDE energy conversion system is designed with cogeneration configuration in the Rankine cycle. To ensure the effectiveness of its cogeneration, the outlet temperature of the RDE is set at 700°C and steam generator outlet temperature is around 530°C. Analysis of the performance of the energy conversion system in various power levels is needed to determine the RDE operating conditions. This research is aimed to study the performance characteristics of RDE energy conversion systems in various reactor power conditions. The analysis was carried out by simulating thermodynamic parameter calculations on the RDE energy conversion system and the overall cooling system using the ChemCad program package. The simulation is carried out by increasing the reactor power from 0 MW to 10 MW at constant pressure and constant mass flow rate. The simulation results show that the steam fraction at the steam generator outlet increases starting from 3 MW reactor power and reaches saturated steam after the thermal power level of 7.5 MW. From the results, it can be concluded that with constant mass flow rate and operating pressure, optimal turbine power is obtained after the reactor thermal power reached 7.5 MW.

Keywords: RDE, Energy Conversion System, Performance, Reactor Power, ChemCad


Full Text:

PDF

References


  1. Grape S., Jacobsson Svärd S., Hellesen C., Jansson P., Åberg Lindell M. New perspectives on nuclear power-Generation IV nuclear energy systems to strengthen nuclear non-proliferation and support nuclear disarmament. Energy Policy. 2014. 73:815–9.
  2. Locatelli G., Mancini M., Todeschini N. Generation IV nuclear reactors: Current status and future prospects. Energy Policy. 2013. 61:1503–20.
  3. Pradeep Varma G. V., Srinivas T. Design and analysis of a cogeneration plant using heat recovery of a cement factory. Case Stud. Therm. Eng. 2015. 5:24–31.
  4. Verfondern K., Yan X., Nishihara T., Allelein H. Safety concept of nuclear cogeneration of hydrogen and electricity. Int. J. Hydrogen Energy. 2017. 42(11):7551–9.
  5. Yan X., Noguchi H., Sato H., Tachibana Y., Kunitomi K., Hino R. A hybrid HTGR system producing electricity, hydrogen and such other products as water demanded in the Middle East. Nucl. Eng. Des. 2014. 271:20–9.
  6. Pirmohamadi A., Ghazi M., Nikian M. Optimal design of cogeneration systems in total site using exergy approach. Energy. 2019. 166:1291–302.
  7. Sato H., Yan X.L., Tachibana Y., Kato Y. Assessment of load-following capability of VHTR cogeneration systems. Ann. Nucl. Energy. 2012. 49:33–40.
  8. Alonso G., Ramirez R., Castillo R. Process heat cogeneration using a high temperature reactor. Nucl. Eng. Des. 2014. 280:137–43.
  9. BATAN The Document Preparation of Preliminary Engineering Design of The Experimental Power Reactor “Conceptual Design of Nuclear Steam Supply System” (RDE/DS-WBS02-201). 2015.
  10. Dibyo S., Irianto I.D. Design analysis on operating parameter of outlet temperature and void fraction in RDE steam generator. Tri Dasa Mega. 2017. 19(1):33–40.
  11. Irianto I.D., Sriyono, Kusumastuti R., Santoso K., Subiyah H., Citra A., et al. Effect of Superheated Steam Pressure on the Performance of RDE Energy Conversion System. J. Phys. Conf. Ser. 2019. 1198:022045.
  12. Dibyo S., Irianto I.D., Bakhri S. Comparison on Two Option Design of The RDE Cogeneration System. J. Phys. Conf. Ser. 2019. 1198:022039.
  13. Dibyo S., Sunaryo G.R., Bakhri S., Irianto I.D. Analysis on Operating Parameter Design to Steam Methane Reforming in Heat Application RDE. J. Phys. Conf. Ser. 2018. 962:012052.
  14. Irianto I.D., Dibyo S., Salimy D.H., Pane J.S. Thermodynamic Analysis On Rankine Cycle Steam For Cogeneration Systems RGTT200K. in: Seminar Nasional Teknologi Energi Nuklir 2016. 2016. pp. 865–72.
  15. Kadarno P., Park D.S., Mahardika N., Irianto I.D., Nugroho A. Fatigue Evaluation of Pressure Vessel using Finite Element Analysis based on ASME BPVC Sec . VIII Division 2. J. Phys. Conf. Ser. 2019. 1198:042015.
  16. Maerani R., Deswandri, Santoso S., Sudarno, Irianto I.D. Reverse Engineering Program Using MBSE to Support Development of I & C System Experimental Power Reactor from PLC to FPGA. J. Phys. Conf. Ser. 2019. 1198:022015.
  17. Irianto I.D., Sriyono, Bakhri S., Dibyo S., Nugroho A. Analysis Of Oxidation Performance In Helium Purification System Of The Indonesia Experimental Power Reactor. Int. J. Mech. Eng. Technol. 2018. 9(13):1348–56.
  18. Solanki K., Patel N. Process Optimization Using CHEMCAD. Int. J. Futur. Trends Eng. Technol. 2014. 1(02):47–51.
  19. Cormos C.-C. Biomass direct chemical looping for hydrogen and power co-production: Process configuration, simulation, thermal integration and techno-economic assessment. Fuel Process. Technol. 2015. 137:16–23.
  20. Dibyo S., Puji Hastuti E., Irianto I.D. Design Analysis Of Cooling System Process Of The Innovative Research Reactor 50 MW. Tri Dasa Mega. 2015. 17(1):19–30.
  21. Zhou Y., Zhou K., Ma Y., Sui Z. Thermal hydraulic simulation of reactor of HTR-PM based on thermal-fluid network and SIMPLE algorithm. Prog. Nucl. Energy. 2013. 62:83–93.
  22. BATAN The Document Preparation of Preliminary Engineering Design of The Experimental Power Reactor “Conceptual Design of Nuclear Steam Supply System” (RDE/DS-WBS02-02A). 2015.
  23. Lee J.J., Ghosh T.K., Loyalka S.K. Oxidation rate of nuclear-grade graphite IG-110 in the kinetic regime for VHTR air ingress accident scenarios. J. Nucl. Mater. 2014. 446(1–3):38–48.
  24. Yanhua Z., Fubing C., Lei S. Analysis of diffusion process and influence factors in the air ingress accident of the HTR-PM. Nucl. Eng. Des. 2014. 271:397–403.
  25. BATAN The Document Preparation of Preliminary Engineering Design of The Experimental Power Reactor “Conceptual Design of Water/Steam Cycle” (RDE/DS-WBS02-207). 2015.
  26. Irianto I.D. Design And Analysis Of Helium Brayton Cycle For Energy Conversion System Of RGTT200K. Tri Dasa Mega. 2016. 18(2):75–86.


Refbacks

  • There are currently no refbacks.


PTKRN Digital Library Mendeley
slot gacor slot