DOI QR코드

DOI QR Code

Study on analog-based ex-core neutron flux monitoring systems of Korean nuclear power plants for digitization

  • Kim, Young Baik (Electronic Engineering Department, Jeonbuk National University) ;
  • Vista, Felipe P. IV (Advanced Electronic Research Information Center, Jeonbuk National University) ;
  • Chong, Kil To (Electronic Engineering Department, Jeonbuk National University)
  • Received : 2020.09.29
  • Accepted : 2021.01.19
  • Published : 2021.07.25

Abstract

The analog-based Ex-core Neutron Flux Monitoring System (ENFMS) in Korean Nuclear Power Plants (NPPs) has been performing its intended functions successfully for a long time. On the other hand, the primary concern with the extended use of analog systems is the aging effect, such as mechanical failures, environmental degradation, and obsolescence. The transition to a digital-based Man-Machine Interface Systems (MMIS) in Korea and other countries has been accelerating, but some systems are still analog-based IC systems, such as the ENFMS in APR1400 NPPs. Digitalized ENFMS can become a reality using computers and microprocessors owing to the progress in digital electronics and information technology. This paper presents the result of the first phase of the research on the digitalization of the ENFMS signal processing electronics for NPPs operated or produced in Korea. It has two main parts: (1) review engineering bases of ex-core neutron flux monitoring system, including nuclear engineering, instrumentation techniques, and analog and digital signal processing techniques, and (2) analysis of analog signal processing electronics of ENFMS for OPR1000 and APR1400 power plants. They are prerequisite to the second phase of the research which is the detailed implementation of the digitalization.

Keywords

Acknowledgement

This work was supported by "Human Resources Program in Energy Technology" of the Korea Institute of Energy Technology Evaluation and Planning (KETEP), granted financial resource from the Ministry of Trade, Industry & Energy, Republic of Korea. (No. 20204010600470). It is also supported in part by the National Research Foundation (NRF) of Korea, funded by the Korean Government (MSIT) (No. 2020R1A2C2005612).

References

  1. G.F. Knoll, Radiation Detection and Measurement, John Wiley & Sons, 2010.
  2. C.J. Artaud, S. Yang, SHIDAOWAN HTR Ex-Core Neutron Flux Monitoring Systems, 2014.
  3. B.-S. Koo, J.-S. Song, C.-C. Lee, K.-K. Kim, Characteristics of an Ex-Core Detector for the Design of SMART ENFMS, 2008.
  4. Y.B. Kim, K.H. Jeong, J.H. Yun, S.C. Kim, Design Specification for Startup and Control Channel in the Ex-Core Neutron Flux Monitoring System, 3N649-ICDs810-02, Rev. 3, KEPCO E&C (NSSS Division), Mar. 2017.
  5. N.R. Council, Digital Instrumentation and Control Systems in Nuclear Power Plants: Safety and Reliability Issues, National Academies Press, 1997.
  6. R. Aryaeinejad, J.K. Hartwell, D.F. Spencer, Comparison between digital and analog pulse shape discrimination techniques for neutron and gamma ray separation, in: IEEE Nuclear Science Symposium Conference Record, vol. 1, 2005, pp. 500-504, 2005.
  7. Y.B. Kim, F.P. Vista, S.B. Cho, K.T. Chong, Digitalization of the ex-core neutron flux monitoring system for APR1400 nuclear power plant, Appl. Sci. 10 (23) (2020), https://doi.org/10.3390/app10238331.
  8. E. Suzuki, A method for measuring absolute reactor power through neutron fluctuation, J. Nucl. Sci. Technol. 3 (3) (1966) 98-105. https://doi.org/10.1080/18811248.1966.9732284
  9. Us Department of Energy, U.S. DoE Fundamentals Handbook - Nuclear Physics and Reactor Theory (DOE-HDBK-1019/2-93), US Department of Energy, Jan. 1993 [Online]. Available, http://large.stanford.edu/courses/2014/ph241/alnoaimi2/docs/Nuclear-Volume2.pdf.
  10. J.G. Ahn, H.R. Hwang, Evaluation of spatial weighting functions for ex-core detectors by adjoint MCNP calculation, in: Presented at the 4 Brazilian Meeting on Nuclear Applications, Aug. 1997. Brazil.
  11. Us Department of Energy, U.S. DoE Fundamentals Handbook - Instrumentation and Control (Module 6 Radiation Detectors, US Department of Energy, Jan. 1993 [Online]. Available, https://www.standards.doe.gov/standardsdocuments/1000/1013-bhdbk-1992-v2/@@images/file.
  12. A.R. Jones, A Novel Detection System Using Neutron/gamma Pulse Shape Discrimination, for Use in Active Interrogation Environments, Lancaster University, 2016.
  13. M. Nakhostin, Signal Processing for Radiation Detectors, John Wiley & Sons, 2017.
  14. G. Grosshoeg, Neutron ionization chambers, Nucl. Instrum. Methods 162 (1) (Jun. 1979) 125-160, https://doi.org/10.1016/0029-554X(79)90710-9.
  15. M. Amiri, Discrimination of Neutron and Photon Signals, Ph. D. Dissertation, Masaryk University 2012, Brno, 2012 (in chinese), 2012.
  16. M. Nakhostin, Recursive algorithms for real-time digital ${\rm CR}\!-\!({\rm RC})^{\rm n}$ pulse shaping, IEEE Trans. Nucl. Sci. 58 (5) (Oct. 2011) 2378-2381, https://doi.org/10.1109/TNS.2011.2164556.
  17. S. Pongpun, A Neutron Measurement System Design for Pulsed Triga Reactor Experiment at Texas A&M University, Faculty of Graduate Studies and Research, University of Regina, 2016.
  18. C.H. Vincent, Random Pulse Trains: Their Measurement and Statistical Properties, 1973.
  19. H. Arahmane, E.-M. Hamzaoui, R.C. El Moursli, Neutron flux monitoring based on blind source separation algorithms in Moroccan TRIGA MARK II reactor, Science and Technology of Nuclear Installations (2017) 2017.
  20. D.A. Gwinn, W.M. Trenholme, A log N and period amplifier utilizing statistical fluctuation signals from a neutron detector, IEEE Trans. Nucl. Sci. 10 (2) (1963) 1-9. https://doi.org/10.1109/TNS2.1963.4315445
  21. W.M. Trenholme, D.J. Keefe, A neutron flux measuring channel covering ten decades of reactor power with a single fixed-position detector, IEEE Trans. Nucl. Sci. 14 (1) (1967) 253-260. https://doi.org/10.1109/TNS.1967.4324424
  22. N.R. Campbell, V.J. Francis, A theory of valve and circuit noise, Journal of the Institution of Electrical Engineers-Part III: Radio and Communication Engineering 93 (21) (1946) 45-52. https://doi.org/10.1049/ji-3-2.1946.0009
  23. B. Geslot, et al., Method to calibrate fission chambers in Campbelling mode, in: 2011 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications, 2011, pp. 1-4.
  24. L. Vermeeren, et al., Experimental verification of the fission chamber gamma signal suppression by the campbelling mode, IEEE Trans. Nucl. Sci. 58 (2) (2011) 362-369. https://doi.org/10.1109/TNS.2011.2113356
  25. P.E. Pakos, A Voltage Squaring Circuit and Analog to Digital Converter, Massachusetts Institute of Technology, 1965.
  26. S. Joo, J.B. Lee, S.M. Seo, Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor, Nuclear Engineering and Technology 50 (1) (2018) 203-210. https://doi.org/10.1016/j.net.2017.10.011