TY - GEN
T1 - Core Power Modelling of High-Temperature Engineering Test Reactor (HTTR) Using Nonlinear Least Squares Method for Parameter Estimation
AU - Istiqomah, Aulia
AU - Subiantoro, Aries
N1 - Funding Information:
ACKNOWLEDGMENT This research is supported by the research grant from Universitas Indonesia, Publikasi Terindeks Internasional (PUTI) Prosiding year 2020; no. NKB-3750/UN2.RST/HKP.05.00/2020. The authors would like to thank Muhammad Subekti from the Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency, for the HTTR experimental data.
Funding Information:
This research is supported by the research grant from Universitas Indonesia, Publikasi Terindeks Internasional (PUTI) Prosiding year 2020; no. NKB-3750/UN2.RST/HKP.05.00/2020. The authors would like to thank Muhammad Subekti from the Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency, for the HTTR experimental data.
Publisher Copyright:
© 2021 IEEE.
PY - 2021/4/28
Y1 - 2021/4/28
N2 - The high-temperature gas cooled-reactor (HTGR) has been constructed in Japan and produces rated power operation and hydrogen, contributing to the development of future energy strategies. One type of HTGR, the high-temperature engineering test reactor (HTTR), uses long hexagonal fuel assemblies. The HTTR is a graphite-moderated, helium-gas-cooled reactor with thermal power of 30 MW, an inlet coolant temperature of 395° C, and an outlet coolant temperature of 950° C. In this paper, a nonlinear mathematical model of the nuclear reactor core was derived in derivative form using fundamental principles. Unknown parameter data could be estimated with physics equations using the nonlinear least squares curve fitting method. The validation between the mathematical model and experimental data of the plant-obtained simulation response indicates that the model could have been used for further optimization and control. The simulation-response results showed that the mathematical model with estimated parameters has an accuracy above 89%. Consequently, based on the simulation response, the mathematical model could be used as the HTTR continues to function.
AB - The high-temperature gas cooled-reactor (HTGR) has been constructed in Japan and produces rated power operation and hydrogen, contributing to the development of future energy strategies. One type of HTGR, the high-temperature engineering test reactor (HTTR), uses long hexagonal fuel assemblies. The HTTR is a graphite-moderated, helium-gas-cooled reactor with thermal power of 30 MW, an inlet coolant temperature of 395° C, and an outlet coolant temperature of 950° C. In this paper, a nonlinear mathematical model of the nuclear reactor core was derived in derivative form using fundamental principles. Unknown parameter data could be estimated with physics equations using the nonlinear least squares curve fitting method. The validation between the mathematical model and experimental data of the plant-obtained simulation response indicates that the model could have been used for further optimization and control. The simulation-response results showed that the mathematical model with estimated parameters has an accuracy above 89%. Consequently, based on the simulation response, the mathematical model could be used as the HTTR continues to function.
KW - Control Rod
KW - Core
KW - Estimation
KW - HTTR
KW - Model
KW - Nonlinear Least Square
KW - Withdrawal
UR - http://www.scopus.com/inward/record.url?scp=85113881319&partnerID=8YFLogxK
U2 - 10.1109/AIMS52415.2021.9466041
DO - 10.1109/AIMS52415.2021.9466041
M3 - Conference contribution
AN - SCOPUS:85113881319
T3 - AIMS 2021 - International Conference on Artificial Intelligence and Mechatronics Systems
BT - AIMS 2021 - International Conference on Artificial Intelligence and Mechatronics Systems
PB - Institute of Electrical and Electronics Engineers Inc.
T2 - 2021 International Conference on Artificial Intelligence and Mechatronics Systems, AIMS 2021
Y2 - 28 April 2021 through 30 April 2021
ER -