Nuclear Engineering and Technology

  • 제54권5호
  • /
  • Pages.1698-1711
  • /
  • 2022
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Application of a combined safety approach for the evaluation of safety margin during a Loss of Condenser Vacuum event

  • Shin, Dong-Hun (Department of Quantum and Nuclear Engineering, Sejong University) ;
  • Jeong, Hae-Yong (Department of Quantum and Nuclear Engineering, Sejong University) ;
  • Park, Moon-Ghu (Department of Quantum and Nuclear Engineering, Sejong University) ;
  • Sohn, Jung-Uk (ZettaCognition)
  • 투고 : 2021.09.08
  • 심사 : 2021.11.06
  • 발행 : 2022.05.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

A combined safety approach, which uses a best-estimate computer code and adopts conservative assumptions for safety systems availability, is developed and applied to the safety margin evaluation for the Loss of Condenser Vacuum (LOCV) of the 1000 MWe Korean Nuclear Power Plant. The Multi-dimensional Analysis of Reactor Safety-KINS standard (MARS-KS) code is selected as a best-estimate code and the PAPIRUS program is used to obtain different initial operational conditions through random sampling of control variables. During an LOCV event, fuel integrity is not threatened by the increase in Departure from Nuclear Boiling Ratio (DNBR). However, the high pressure in the primary coolant system and the secondary system might affect the system integrity. Thus, the peak pressure becomes a major safety concern. Transient analyses are performed for 124 cases of different initial conditions and the most conservative case, which results in the highest system pressure is selected. It is found the suggested methodology gives similar peak pressures when compared to those predicted from existing methodologies. The proposed approach is expected to minimize the time and efforts required to identify the conservative plant conditions in the existing conservative safety methodologies.

키워드

과제정보

This research was supported by Basic Science Research Program through the National Research Foundation of Korea (NRF) funded by the Ministry of Science, ICT & Future Planning (NRF-2016R1A5A1013919) and by the Korea Foundation of Nuclear Safety (KoFONS) grant funded by the Nuclear Safety and Security Commission (NSSC) of Republic of Korea (No.2101062).

참고문헌

  1. IAEA, Safety Margins of Operating Reactors: Analysis of Uncertainties and Implications for Decision Making, IAEA, 2003. IAEA-TECDOC-1332.
  2. L.L. Briggs, Uncertainty quantification approaches for advanced reactor analyses, Argonne Natl. Lab. (2008). ANL-GenIV-110.
  3. Korea Institute of Nuclear Safety, Regulatory Guidelines for Light Water Reactors, KINS, KINS/GE-N001, 2015.
  4. W.P. Baek, J.E. Yang, J.J. Ha, Safety assessment of Korean nuclear facilities: current status and future, Nucl. Eng. Technol. 41 (2009) 391-402. https://doi.org/10.5516/NET.2009.41.4.391
  5. IAEA, Deterministic Safety Analysis for Nuclear Power Plants, IAEA, 2019. IAEA SSG-2, Rev. 1.
  6. K.-H. Lee, M.-G. Kim, J.I. Lee, P.-S. Lee, Recent advances in ocean nuclear power plants, Energies 8 (2015) 11470-11492. https://doi.org/10.3390/en81011470
  7. Y.-H. Shin, S. Park, B.S. Kim, S. Choi, I.S. Hwang, Small modular reactor (SMR) development plan in Korea, in: AIP Conf. Proceedings 1659, 2015, 020002.
  8. Korea Atomic Energy Research Institute, MARS Code Manual, Volume IV: Developmental Assessment Report, KAERI, 2006. KAERI/TR-3042/2005.
  9. KHNP, Korea Non-LOCA Analysis Package, KHNP, 2007. TR-KHNP-0009 (in Korean).
  10. M.P. Paulsen, et al., RETRAN-3D: a program for transient thermal-hydraulic analysis of complex fluid flow systems, Electric Power Research Institute (2001). EPRI NP-7450.
  11. E.J. Lee, C.S. Lee, J.J. Sohn, Analysis of a loss of condenser Vacuum event using the SPACE code, in: Transaction of Korean Nuclear Society Autumn Meeting, 2011. Gyeongju (Korea), Oct. 27-28.
  12. E.J. Lee, C.E. Park, M.S. Park, J.Y. Huh, G.C. Lee, Evaluation on the simulation capability of SPACE code with respect to system pressurization, in: Transaction of Korean Nuclear Society Spring Meeting, 2017. Jeju (Korea), May 18-19.
  13. Jaeseok Heo, Kyung Doo Kim, PAPIRUS, a parallel computing framework for sensitivity analysis, uncertainty propagation, and estimation of parameter distribution, Nucl. Eng. Des. 292 (2015) 237-247. https://doi.org/10.1016/j.nucengdes.2015.07.002
  14. C. Jang, K. Um, Applications of integrated safety analysis methodology to reload safety evaluation, Nucl. Eng. Technol. 43 (2011) 187-193. https://doi.org/10.5516/NET.2011.43.2.187
  15. KEPCO, Final Safety Analysis Report, Uljin 3, 4, KEPCO, 1998.
  16. Combustion Engineering Inc, CESEC Digital Simulation of a Combustion Engineering Nuclear Steam Supply System, Combustion Engineering, 1981. LD-82-001.