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Effect analysis of ISLOCA pathways on fission product release at Westinghouse 2-loop PWR using MELCOR

  • Kim, Seungwoo (Department of Nuclear Engineering, Hanyang University) ;
  • Park, Yerim (Department of Nuclear Engineering, Hanyang University) ;
  • Jin, Youngho (Department of Nuclear Engineering, Hanyang University) ;
  • Kim, Dong Ha (Department of Nuclear Engineering, Hanyang University) ;
  • Jae, Moosung (Department of Nuclear Engineering, Hanyang University)
  • Received : 2020.10.05
  • Accepted : 2021.03.20
  • Published : 2021.09.25

Abstract

As the amount of fission product released from ISLOCA was overestimated because of conservative assumptions in the past, several studies have been recently conducted to evaluate the actual release amount. Among several pathways for the ISLOCA, most studies were focused on the pathway with the highest possibility. However, different ISLOCA pathways may have different fission product release characteristics. In this study, fission product behavior was analyzed for various pathways at the Westinghouse two-loop plant using MELCOR. Four pathways are considered: the pipes from a cold leg, from a downcomer, from a hot leg to the outlet of RHR heat exchanger, and the pipe from the hot leg to the inlet of RHR pump (Pathway 1-4). According to the analysis results, cladding fails at around 2.5 h in Pathways 1 and 2, and on the other hand, about 3.3 h in Pathways 3 and 4 because the ISLOCA pathways affect the safety injection flow path. While the release amount of cesium and iodine ranges between 20 and 26% in Pathways 1 to 3, Pathway 4 allows only 5% to the environment because the break location is submerged. Also, as more than 90% of cesium released to the environment passes through the personnel door, reinforcing the pressure capacity of the doors would be a significant factor in the accident management of the ISLOCA.

Keywords

Acknowledgement

This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KOFONS), granted financial resource from the Multi-Unit Risk Research Group (MURRG), Republic of Korea (No. 1705001).

References

  1. N. Rasmussen, et al., Reactor Safety Study; an Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, U.S. Nuclear Regulatory Commission, 1975. Appendix I, WASH-1400 (NUREG-75/014).
  2. Denwood Ross, et al., Severe accident risks: an assessment for five U.S. Nuclear power plants, U.S. Nuclear Regulatory Commission 2 (1990). Appendix C, NUREG-1150.
  3. W.J. Galyean, et al., Assessment of ISLOCA Risk- Methodology and Application to a Babcock and Wilcox Nuclear Power Plant, vol. 1, Idaho National Engineering Laboratory, 1992. NUREG/CR-5604.
  4. Korea Hydro & Nuclear Power Co. Ltd, Probabilistic Safety Assessment Report for Kori Unit 2, Initiating Event Analysis, 2003.
  5. Sandia National Laboratories, State-of-the-Art Reactor Consequence Analyses Project. Volume 2: Surry Integrated Analysis, vol. 2, 2013. NUREG/CR-7110.
  6. Seok-Jung Han, et al., An improvement of estimation method of source term to the environment for interfacing system LOCA for typical PWR using MELCOR code, Journal of Radiation Protection and Research (2017), https://doi.org/ 10.14407/jrpr.2017.42.2.106.
  7. Lee Keo-hyoung, et al., Analyses of fission product retention under ISLOCA using MELCOR for APR1400, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 23-24, 2019.
  8. McMinn Paul, et al., Source term analysis for PWR ISLOCA using MAAP5, in: PSA 2019, Charleston, USA, April 28-May 3, 2019.
  9. L.L. Humphries, et al., MELCOR Computer Code Manuals Vol. 1: Primer and Users' Guide, Sandia National Laboratories, 2019. SAND2019-12536O.
  10. L.L. Humphries, et al., MELCOR Computer Code Manuals Vol. 2: Reference Manual, Sandia National Laboratories, 2019. SAND2019-12537O.
  11. Korea Hydro & Nuclear Power Co., Ltd, Final Safety Analysis Report for Kori Unit 2, 1989.
  12. Alan V. Jones, et al., Circuit and Containment Aspects of PHEBUS Experiments FPT0 and FPT1, European Commission, 2015. JRC95357/EUR 27218 EN.
  13. Marco Sangiorgi, et al., Circuit and Containment Aspects of PHEBUS Experiment FPT-2, European Commission, 2015. JRC99477/EUR 27631 EN.
  14. O. Randall, Gauntt, Synthesis of VERCORS and Phebus Data in Severe Accident Codes and Applications, Sandia National Laboratories, 2010. SAND2010-1633.
  15. F. Gelbard, MAEROS User Manual, Sandia National Laboratories, 1982. SAND80-0822(NUREG/CR-1391).
  16. F.G. Di Lemma, et al., Experimental investigation of the influence of Mo contained in stainless steel on Cs chemisorption behavior, J. Nucl. Mater. 484 (2017) 174-182. https://doi.org/10.1016/j.jnucmat.2016.11.031