Improvement of a Code-Based Kartini Reactor Simulator for Education and Training

- Sutanto (1), Intan Nafisah (2), Anhar R. Antariksawan (3), Jianhui Wu (4)
(1) Polytechnic Institute of Nuclear Technology, Babarsari Street, Yogyakarta, 55281, Indonesia
(2) Polytechnic Institute of Nuclear Technology, Babarsari Street, Yogyakarta, 55281, Indonesia
(3) Center for Research of Accelerator Technology-National Innovation and Research Agency, Babarsari Street, Yogyakarta, 55281, Indonesia
(4) Center for Thorium Molten Salt Reactor System, Shanghai Institute of Applied Physics, Chinese Academy of Science, Jiading Campus, Shanghai 201800, P.R. China
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How to cite (IJASEIT) :
Sutanto, -, et al. “Improvement of a Code-Based Kartini Reactor Simulator for Education and Training”. International Journal on Advanced Science, Engineering and Information Technology, vol. 13, no. 4, Aug. 2023, pp. 1430-7, doi:10.18517/ijaseit.13.4.18282.
A code-based Kartini reactor simulator was improved as a facility for the human resource development of a nuclear reactor. The simulator simulates the plant dynamics regarding a change of a control rod position. Reactor operation parameter calculations of the reactor power, coolant flow, and fuel temperatures adopt a one-channel method with assumptions of homogeneous radial power distribution and a cosine function of the axial power distribution. Point reactor kinetics, radial conduction heat transfer, and mass and energy conservation are the calculation code's governing equations. Reactivity feedback due to the coolant density and fuel temperature changes are considered. Reactor pressure is fixed at 1 atm due to an open pool-type research reactor. A graphical user interface was developed to operate the simulator. The operation results of the simulator show that the power calculation agrees well with the experimental data. An accident of excess reactivity due to a control ejection is assumed to happen, causing a positive reactivity insertion of 1.11$. However, the safety criterion of the cladding temperature is satisfied due to the negative reactivity feedback. Besides, early application of 3D virtual reality was carried out to provide an immersive interaction between the users and the virtual Kartini reactor plant. The further development of integrating both the virtual reality and the simulator in the recent Kartini reactor-based internet reactor laboratory is interesting to provide a facility with features of remote as well as immersive education and training.

M. Tsuboi et al., “Disaster-related deaths after the Fukushima Daiichi nuclear power plant accident - Definition of the term and lessons learned,” Environ. Adv., vol. 8, no. September 2021, p. 100248, 2022, doi: 10.1016/j.envadv.2022.100248.

G. R. Skillman and J. L. Rempe, “The Three Mile Island Unit 2 Accident,” Encycl. Nucl. Energy, pp. 17-29, 2021.

D. Holiaka, S. Fesenko, V. Kashparov, V. Protsak, S. Levchuk, and M. Holiaka, “Effects of radiation on radial growth of Scots pine in areas highly affected by the Chernobyl accident,” J. Environ. Radioact., vol. 222, no. May, p. 106320, 2020, doi: 10.1016/j.jenvrad.2020.106320.

K. A. Jordan, D. Springfels, and D. Schubring, “Modern design and safety analysis of the University of Florida Training Reactor,” Nucl. Eng. Des., vol. 286, pp. 89-93, 2015, doi: 10.1016/j.nucengdes.2015.01.019.

J. Alnaqbi, D. Hartanto, R. Alnuaimi, M. Imron, and V. Gillette, “Static and transient analyses of Advanced Power Reactor 1400 (APR1400) initial core using open-source nodal core simulator KOMODO,” Nucl. Eng. Technol., vol. 54, no. 2, pp. 764-769, 2022, doi: 10.1016/j.net.2021.08.012.

B. Cui and J. Jiang, “Development of an engineering simulator for a physical component based nuclear process control test facility,” Simul. Model. Pract. Theory, vol. 71, pp. 83-101, 2017, doi: 10.1016/j.simpat.2016.11.006.

Y. Zhao and C. Smidts, “A method for systematically developing the knowledge base of reactor operators in nuclear power plants to support cognitive modeling of operator performance,” Reliab. Eng. Syst. Saf., vol. 186, no. December 2018, pp. 64-77, 2019, doi: 10.1016/j.ress.2019.02.014.

A. T. Bouma, Q. J. Wei, J. E. Parsons, J. Buongiorno, and J. H. Lienhard, “Energy and water without carbon: Integrated desalination and nuclear power at Diablo Canyon,” J. Appl. Energy, vol. 323, p. 119612, 2022.

M. Ho, E. Obbard, P. A. Burr, and G. Yeoh, “A review on the development of nuclear power reactors,” Energy Procedia, vol. 160, no. 2018, pp. 459-466, 2019, doi: 10.1016/j.egypro.2019.02.193.

W. S. Kim, S. H. Hong, H. S. Choi, S. R. Choi, and D. J. Euh, “Design and validation of a fuel assembly simulator for PGSFR reactor flow distribution test facility,” Nucl. Eng. Des., vol. 356, no. May, p. 110353, 2020, doi: 10.1016/j.nucengdes.2019.110353.

J. Wu et al., “A novel concept for a molten salt reactor moderated by heavy water,” Ann. Nucl. Energy, vol. 132, pp. 391-403, 2019, doi: 10.1016/j.anucene.2019.04.043.

J. Wu, C. Yu, C. Zou, G. Jia, X. Cai, and J. Chen, “Influences of reprocessing separation efficiency on the fuel cycle performances for a Heavy Water moderated Molten Salt Reactor,” Nucl. Eng. Des., vol. 380, no. April, p. 111311, 2021, doi: 10.1016/j.nucengdes.2021.111311.

M. Imron, “Development and verification of open reactor simulator ADPRES,” Ann. Nucl. Energy, vol. 133, pp. 580-588, 2019, doi: 10.1016/j.anucene.2019.06.049.

J. Malec, D. ToÅ¡kan, and L. Snoj, “PC-based JSI research reactor simulator,” Ann. Nucl. Energy, vol. 146, p. 107630, 2020, doi: 10.1016/j.anucene.2020.107630.

S. Lyu, D. Lu, and D. Sui, “Neutronics benchmark analysis of the EBR-II SHRT-45R with SAC-3D,” Nucl. Eng. Des., vol. 364, no. May, p. 110679, 2020, doi: 10.1016/j.nucengdes.2020.110679.

P. Suk, O. Chví¡la, I. G. Maldonado, and J. Rataj, “Evaluation of end of cycle plutonium isotopic content in a VVER-1000 reactor using a 3D full-core simulator,” Nucl. Eng. Des., vol. 377, no. August 2020, p. 111133, 2021, doi: 10.1016/j.nucengdes.2021.111133.

Y. Yu et al., “Research and development of a transient thermal-hydraulic code for system safety analysis of sodium cooled fast reactor,” Ann. Nucl. Energy, vol. 152, p. 107841, 2021, doi: 10.1016/j.anucene.2020.107841.

T. Meng, K. Cheng, F. Zhao, C. Xia, and S. Tan, “Dynamic simulation of the gas-cooled space nuclear reactor system using SIMCODE,” Ann. Nucl. Energy, vol. 159, p. 108293, 2021, doi: 10.1016/j.anucene.2021.108293.

M. Alqahtani, A. Buijs, and S. E. Day, “Experimental measurement and Monte Carlo code simulation of the gamma heating at different irradiation sites in a nuclear research reactor,” Nucl. Eng. Des., vol. 364, no. May, p. 110690, 2020, doi: 10.1016/j.nucengdes.2020.110690.

T. Liu, Z. Wu, C. Lu, and R. P. Martin, “A best estimate plus uncertainty safety analysis framework based on RELAP5-3D and RAVEN platform for research reactor transient analyses,” Prog. Nucl. Energy, vol. 132, no. December 2020, p. 103610, 2021, doi: 10.1016/j.pnucene.2020.103610.

S. Safaei Arshi, M. Amin Mozafari, A. Jozvaziri, and S. M. Mirvakili, “Investigation of safety aspects during steady state operation of Tehran research reactor fuel test loop,” Prog. Nucl. Energy, vol. 140, no. December 2020, p. 103895, 2021, doi: 10.1016/j.pnucene.2021.103895.

K. O. Kim, G. Roh, and B. Lee, “Neutronic performance of the hybrid-low power research reactor for education and neutron applications,” Ann. Nucl. Energy, vol. 158, p. 108272, 2021, doi: 10.1016/j.anucene.2021.108272.

I. Kovar, “Use of virtual reality as a tool to overcome the post-traumatic stress disorder of pensioners,” Int. J. Adv. Sci. Eng. Inf. Technol., vol. 9, no. 3, pp. 841-848, 2019, doi: 10.18517/ijaseit.9.3.8245.

J. D. Abril, O. Rivera, O. I. Caldas, M. F. Mauledoux, and O. F. Avilí©s, “Serious game design of virtual reality balance rehabilitation with a record of psychophysiological variables and emotional assessment,” Int. J. Adv. Sci. Eng. Inf. Technol., vol. 10, no. 4, pp. 1519-1525, 2020, doi: 10.18517/ijaseit.10.4.10319.

Z. Guo et al., “Applications of virtual reality in maintenance during the industrial product lifecycle: A systematic review,” J. Manuf. Syst., vol. 56, no. May 2019, pp. 525-538, 2020, doi: 10.1016/j.jmsy.2020.07.007.

S. Qin, Q. Wang, and X. Chen, “Application of virtual reality technology in nuclear device design and research,” Fusion Eng. Des., vol. 161, no. March, p. 111906, 2020, doi: 10.1016/j.fusengdes.2020.111906.

L. Gabcan, A. S. M. Alves, and P. F. Frutuoso e Melo, “3D simulation model of water infiltration for radioactive waste on a virtual reality Environment: An application to the Abadia de Goií¡s repository,” Ann. Nucl. Energy, vol. 140, p. 107265, 2020, doi: 10.1016/j.anucene.2019.107265.

Y. Wu, “Development and application of virtual nuclear power plant in digital society environment,” Int. J. Energy Res., vol. 43, no. 4, pp. 1521-1533, 2019, doi: 10.1002/er.4378.

K. Hagita, Y. Kodama, and M. Takada, “Simplified virtual reality training system for radiation shielding and measurement in nuclear engineering,” Prog. Nucl. Energy, vol. 118, no. August 2019, p. 103127, 2020, doi: 10.1016/j.pnucene.2019.103127.

A. Das, M. S. Hossain, M. K. A. Rabby, and R. Barman, “Virtual reactor laboratory integrated with cyber security from Bangladesh perspective,” Int. J. Adv. Nucl. React. Des. Technol., vol. 3, no. October 2021, pp. 184-193, 2021, doi: 10.1016/j.jandt.2021.09.005.

S. Syarip and P. I. Wahyono, “Experience in nuclear reactor physics laboratory exercises using Kartini research reactor,” J. Phys. Conf. Ser., vol. 1157, no. 3, 2019, doi: 10.1088/1742-6596/1157/3/032002.

Sutanto, A. M. D. Suryana, and Syarip, “Development of Kartini Reactor Code to Support Nuclear Training Center and Safety Analysis,” 2018 4th Int. Conf. Sci. Technol., vol. 1, pp. 1-6, 2018.

B. Riyono, R. Pulungan, A. Dharmawan, and A. R. Antariksawan, “Experimental investigation on the thermohydraulic parameters of Kartini research reactor under variation of the primary pump flow,” Appl. Therm. Eng., vol. 213, p. 118674, 2022.

US Department of Energy, “Doe Fundamentals Handbook Nuclear Physics Volume 1 of 2,” Nucl. Phys., vol. 1, no. January 1993, p. 36, 2003.

Y. Oka, S. Koshizuka, Y. Ishiwatari, and A. Yamaji, Super Light Water Reactors and Super Fast Reactors. Springer, 2010.

A. S. Ví¡nyi et al., “Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor,” Ann. Nucl. Energy, vol. 155, 2021, doi: 10.1016/j.anucene.2021.108144.

M. K. Rowinski, J. Zhao, T. J. White, and Y. C. Soh, “Safety analysis of Super-Critical Water Reactors-A review,” Prog. Nucl. Energy, vol. 106, no. February, pp. 87-101, 2018, doi: 10.1016/j.pnucene.2018.03.002.

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