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A Systems Engineering Approach to Multi-Physics Load Follow Simulation of the Korean APR1400 Nuclear Power Plant

  • Mahmoud, Abd El Rahman (Nuclear Engineering Department, KEPCO International Nuclear Graduate School) ;
  • Diab, Aya (Nuclear Engineering Department, KEPCO International Nuclear Graduate School)
  • Received : 2020.08.13
  • Accepted : 2020.12.16
  • Published : 2020.12.31

Abstract

Nuclear power plants in South Korea are operated to cover the baseload demand. Hence they are operated at 100% rated power and do not deploy power tracking control except for startup, shutdown, or during transients. However, as the contribution of renewable energy in the energy mix increases, load follow operation may be needed to cover the imbalance between consumption and production due to the intermittent nature of electricity produced from the conversion of wind or solar energy. Load follow operation may be quite challenging since the operators need to control the axial power distribution and core reactivity while simultaneously conducting the power maneuvering. In this paper, a systems engineering approach for multi-physics load follow simulation of APR1400 is performed. RELAP5/SCDAPSIM/MOD3.4/3DKIN multi-physics package is selected to simulate the Korean Advanced Power Reactor, APR1400, under load follow operation to reflect the impact of feedback signals on the system safety parameters. Furthermore, the systems engineering approach is adopted to identify the requirements, functions, and physical architecture to provide a set of verification and validation activities that guide this project development by linking each requirement to a validation or verification test with predefined success criteria.

Keywords

References

  1. Kim, J.S., 2009. Present and future of nuclear power in Korea. In: Presentation Material of International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century.
  2. A. Lokhov, "Technical and economic aspect of load following with nuclear power plants", Nuclear Energy Agency, OECD, June 2011
  3. F. Yousefpour, M. B. Ghofrani, "Improvement of Axial Power Distribution Control Capabilities in VVER- 1000 Reactors", Annals of Nuclear Energy 27, pp.949-957, 2000 https://doi.org/10.1016/S0306-4549(99)00098-5
  4. S. Y. Oh, J. H Chang, J. K. Park, Mode K - A Core Control Logic for Enhanced Load- Follow Operations of A Pressurized Water Reactor, Nuclear Technology, Vol.134, May 2001.
  5. J. I. Choi, S. Y. Oh, J. E. Kuh, Advanced Load Follow Operation Mode for Korean Standardized Nuclear Power Plants, Journal of Korean Nuclear Society Volume 24, Number 2, June 1992.
  6. IAEA-TECDOC-1539, Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants. Vienna: IAEA, 2003.
  7. M. Park, J. Choe, D. Lee, E. Lee, "Application of RAST-K to Simulation of OPR1000 Daily Load Follow Operation", Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, October 30-31, 2014.
  8. M. Park, J. Choe, D. Lee, E. Lee , "Verification of RAST-K Capability for Simulation of OPR1000 Daily Load Follow Operation by Mode K", Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, October 30-31, 2014
  9. F. Zhao, S. Wua, P. Wanga, H. Songa, X. Weia, S. Revankarb, "Modeling and load follow simulation of CPR1000 Nuclear Power Plant implementing Mechanical Shim control strategy", Nuclear Engineering and Design 352 (2019).
  10. A. Kossiakoff, Systems Engineering Principles and Practice 2ndEdition, John Wiley &sons, p139, 2011
  11. I. S. Hwang, J. C. Jung. Development Process of FPGA-based Departure from Nucleate Boiling Ratio Algorithm Using System Engineering Approach, Journal of KOSSE, pp. 41-48, 2018
  12. CRISSUE-S Partners, CRISSUE-S WP-1-Report: Neutronics/Thermal-hydraulics coupling in LWR Technology, Data Requirements and Databases Needed for Transient Simulations and Qualifications (DATABASE, OECD (2004).
  13. CRISSUE-S Partners, CRISSUE-S WP-2-Report: Neutronics/Thermal-hydraulics coupling in LWR Technology: State-of-the-art Report (REAC-SOAR), OECD (2004).
  14. CRISSUE-S Partners, CRISSUE-S WP3-Report: Neutronics/Thermal-hydraulics Coupling in LWR Technology, Achievements and Recommendations Report (FINARES), OECD (2004).