Analysis of Cogeneration Energy Conversion System Design in IPWR Reactor

Authors

  • Ign. Djoko Irianto Research Center for Nuclear Reactor Technology and Safety, BRIN
  • Sriyono Research Center for Nuclear Reactor Technology and Safety, BRIN
  • Sukmanto Dibyo Research Center for Nuclear Reactor Technology and Safety, BRIN
  • Djati Hoesen Salimy Research Center for Nuclear Reactor Technology and Safety, BRIN
  • Tukiran Surbakti Research Center for Nuclear Reactor Technology and Safety, BRIN
  • Rahayu Kusumastuti Research Center for Nuclear Reactor Technology and Safety, BRIN

DOI:

https://doi.org/10.17146/tdm.2022.24.1.6414

Keywords:

Energy Conversion System, Cogeneration, IPWR type reactor, ChemCAD, Energy Utilization Factor

Abstract

The acceleration of national development, especially in the industrial sector, requires an adequate national energy supply. There are various types of energy sources such as conventional energy sources, new and renewable energy sources including nuclear energy. The problem is how to utilize these energy sources into energy that is ready to be utilized. As a research and development institution in the nuclear field, BRIN has taken the initiative to contribute to the development of technology for providing electricity and other thermal energy, particularly reactor technology as a power plant and a provider of thermal energy. This research aims to analyze IPWR type SMR reactor design as a cogeneration energy conversion system. The IPWR reactor coolant as a cogeneration energy conversion system is arranged in an indirect cycle configuration or Rankine cycle. The primary cooling system and the secondary cooling system are mediated by a heat exchanger which also functions as a steam generator. The analysis was carried out by simulation using ChemCAD computer software to study the temperature characteristics and performance parameters of the IPWR as a reactor cogeneration energy conversion system. The simulation results show that the temperature of saturated steam coming out of the steam generating unit is around 505.17 K. Saturated steam is obtained in the reactor power range between 40 MWth to 100 MWth. Energy utilization factor (EUF) calculation shows that the IPWR cogeneration configuration can increase the energy utilization factor value up to 91.20%. The acceleration of national development, especially in the industrial sector, requires an adequate national energy supply. There are various types of energy sources such as conventional energy sources, new and renewable energy sources including nuclear energy. The problem is how to utilize these energy sources into energy that is ready to be utilized. As a research and development institution in the nuclear field, BRIN has taken the initiative to contribute to the development of technology for providing electricity and other thermal energy, particularly reactor technology as a power plant and a provider of thermal energy. This research aims to analyze IPWR type SMR reactor design as a cogeneration energy conversion system. The IPWR reactor coolant as a cogeneration energy conversion system is arranged in an indirect cycle configuration or Rankine cycle. The primary cooling system and the secondary cooling system are mediated by a heat exchanger which also functions as a steam generator. The analysis was carried out by simulation using ChemCAD computer software to study the temperature characteristics and performance parameters of the IPWR as a reactor cogeneration energy conversion system. The simulation results show that the temperature of saturated steam coming out of the steam generating unit is around 505.17 K. Saturated steam is obtained in the reactor power range between 40 MWth to 100 MWth. Energy utilization factor (EUF) calculation shows that the IPWR cogeneration configuration can increase the energy utilization factor value up to 91.20%.

References

Abdussami M.R., Adham M.I., Gabbar H.A. Modeling and performance analysis of nuclear-renewable micro hybrid energy system based on different coupling methods. Energy Reports. 2020. 6(June):189-206.

https://doi.org/10.1016/j.egyr.2020.08.043

Gabbar H.A., Abdussami M.R., Adham M.I. Techno-economic evaluation of interconnected nuclear-renewable micro hybrid energy systems with combined heat and power. Energies. 2020. 13(7)

https://doi.org/10.3390/en13071642

Schmidt J.M., Gude V.G. Nuclear cogeneration for cleaner desalination and power generation - A feasibility study. Clean. Eng. Technol. 2021. 2(November 2020):100044.

https://doi.org/10.1016/j.clet.2021.100044

Pirmohamadi A., Ghazi M., Nikian M. Optimal design of cogeneration systems in total site using exergy approach. Energy. 2019. 166:1291-302.

https://doi.org/10.1016/j.energy.2018.10.167

Sato H., Yan X.L. Study of an HTGR and renewable energy hybrid system for grid stability. Nucl. Eng. Des. 2019. 343(August 2018):178-86.

https://doi.org/10.1016/j.nucengdes.2019.01.010

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.

https://doi.org/10.1016/j.ijhydene.2016.04.239

Sudadiyo S., Irianto I.D., Supriatna P. Analysis On The Axial Turbine Blade Using Fluent For High Temperature Helium-Cooled Reactor (RGTT200K). Semin. Nas. Teknol. Energi Nukl. 2015. 2015.:15-6.

Irianto I.D., Sudadiyo S., Dibyo S. Performance Analysis On RGTT200K Cogeneration System For Changes In The Reactor Coolant Mass Flow Rate. in: Seminar Nasional Teknologi Energi Nuklir 2015. Bali. 2015. pp. 15-6.

Irianto I.D. Design And Analysis Of Helium Brayton Cycle For Energy Conversion System Of RGTT200K. Tri Dasa Mega. 2016. 18(2):75-86.

https://doi.org/10.17146/tdm.2016.18.2.2320

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.

Irianto I.D., Dibyo S., Sriyono, Salimy D.H., Kusumastuti R., Pujiastuti E., et al. Performance analysis on the design of the energy conversion system of the Indonesia experimental power reactor. AIP Conf. Proc. 2019. 2180(December)

https://doi.org/10.1063/1.5135540

Dibyo S., Irianto I.D., Bakhri S. Comparison on Two Option Design of The RDE Cogeneration System. J. Phys.: Conf. Ser. 2019. 1198:022039.

https://doi.org/10.1088/1742-6596/1198/2/022039

Kadarno P., Riyandwita B.W., Sriyono, Irianto I.D. Effect of helium purification system intake pipe on pressure drop of HTGR steam generator. AIP Conf. Proc. 2019. 2180(December)

https://doi.org/10.1063/1.5135539

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.

https://doi.org/10.17146/tdm.2017.19.1.3228

Irianto I.D., Dibyo S., Sriyono S., Salimy D.H., Kusumastuti R., Pancoko M. Performance Analysis of RDE Energy Conversion System in Various Reactor Power Condition. Tri Dasa Mega. 2019. 21(3):99-106.

https://doi.org/10.17146/tdm.2019.21.3.5570

Zeliang C., Mi Y., Tokuhiro A., Lu L., Rezvoi A. Developmental Status , Design Characteristics and. Energies. 2020.

Priego E., Alonso G., del Valle E., Ramirez R. Alternatives of steam extraction for desalination purposes using SMART reactor. Desalination. 2017. 413:199-216.

https://doi.org/10.1016/j.desal.2017.03.018

Dong Z., Pan Y. A lumped-parameter dynamical model of a nuclear heating reactor cogeneration plant. Energy. 2018. 145:638-56.

https://doi.org/10.1016/j.energy.2017.12.153

Dong Z., Liu M., Jiang D., Huang X., Zhang Y., Zhang Z. Automatic generation control of nuclear heating reactor power plants. Energies. 2018. 11(10)

https://doi.org/10.3390/en11102782

Xinhe Q., Xiaoyong Y., Jie W., Gang Z. Combined cycle schemes coupled with a Very High Temperature gas-cooled reactor. Prog. Nucl. Energy. 2018. 108(April):1-10.

https://doi.org/10.1016/j.pnucene.2018.05.001

Chen H., Wu Y., Xu J., Xu G., Yang Y., Liu W., et al. Thermodynamic and Economic Analyses of Reformative Design for High Back-Pressure Heating in Coal-Fueled Cogeneration Units. Entropy. 2019. 21(4):342. 22. Khan S.U. Transient Analysis of Integral Pressurized Water Reactor ( Ipwr ). Int. Conf. Nucl. Energy New Eur. 2013. 4:1-8.

https://doi.org/10.3390/e21040342

Downloads

Published

2022-03-07

How to Cite

Irianto, I. D., Sriyono, Dibyo, S., Salimy, D. H., Surbakti, T., & Kusumastuti, R. (2022). Analysis of Cogeneration Energy Conversion System Design in IPWR Reactor. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 24(1), 19–26. https://doi.org/10.17146/tdm.2022.24.1.6414