Nuclear Engineering and Technology

  • 제54권12호
  • /
  • Pages.4534-4550
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  • 2022
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Effect of mitigation strategies in the severe accident uncertainty analysis of the OPR1000 short-term station blackout accident

  • Wonjun Choi (Department of Nuclear Engineering, Hanyang University) ;
  • Kwang-Il Ahn (Korea Atomic Energy Research Institute) ;
  • Sung Joong Kim (Department of Nuclear Engineering, Hanyang University)
  • 투고 : 2022.02.25
  • 심사 : 2022.07.31
  • 발행 : 2022.12.25
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초록

Integrated severe accident codes should be capable of simulating not only specific physical phenomena but also entire plant behaviors, and in a sufficiently fast time. However, significant uncertainty may exist owing to the numerous parametric models and interactions among the various phenomena. The primary objectives of this study are to present best-practice uncertainty and sensitivity analysis results regarding the evolutions of severe accidents (SAs) and fission product source terms and to determine the effects of mitigation measures on them, as expected during a short-term station blackout (STSBO) of a reference pressurized water reactor (optimized power reactor (OPR)1000). Three reference scenarios related to the STSBO accident are considered: one base and two mitigation scenarios, and the impacts of dedicated severe accident mitigation (SAM) actions on the results of interest are analyzed (such as flammable gas generation). The uncertainties are quantified based on a random set of Monte Carlo samples per case scenario. The relative importance values of the uncertain input parameters to the results of interest are quantitatively evaluated through a relevant sensitivity/importance analysis.

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과제정보

This work was supported by the International Atomic Energy Agency under the Coordinated Research Project award I31033 on Advancing the State-of-Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water-Cooled Reactors, launched in 2019. This work was also supported by a National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIT: Ministry of Science and ICT) (No. 2022M2D2A1A02061334). This work was also partly supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) using the financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2003006-0120-CG100).

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