Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Application case for phase III of UAM-LWR benchmark: Uncertainty propagation of thermal-hydraulic macroscopic parameters

  • Mesado, C. (Institute for the Industrial, Radiophysical and Environmental Safety (ISIRYM), Universitat Politecnica de Valencia) ;
  • Miro, R. (Institute for the Industrial, Radiophysical and Environmental Safety (ISIRYM), Universitat Politecnica de Valencia) ;
  • Verdu, G. (Institute for the Industrial, Radiophysical and Environmental Safety (ISIRYM), Universitat Politecnica de Valencia)
  • Received : 2019.08.20
  • Accepted : 2020.01.12
  • Published : 2020.08.25
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Abstract

This work covers an important point of the benchmark released by the expert group on Uncertainty Analysis in Modeling of Light Water Reactors. This ambitious benchmark aims to determine the uncertainty in light water reactors systems and processes in all stages of calculation, with emphasis on multi-physics (coupled) and multi-scale simulations. The Gesellschaft für Anlagen und Reaktorsicherheit methodology is used to propagate the thermal-hydraulic uncertainty of macroscopic parameters through TRACE5.0p3/PARCSv3.0 coupled code. The main innovative points achieved in this work are i) a new thermal-hydraulic model is developed with a highly-accurate 3D core discretization plus an iterative process is presented to adjust the 3D bypass flow, ii) a control rod insertion occurrence -which data is obtained from a real PWR test- is used as a transient simulation, iii) two approaches are used for the propagation process: maximum response where the uncertainty and sensitivity analysis is performed for the maximum absolute response and index dependent where the uncertainty and sensitivity analysis is performed at each time step, and iv) RESTING MATLAB code is developed to automate the model generation process and, then, propagate the thermal-hydraulic uncertainty. The input uncertainty information is found in related literature or, if not found, defined based on expert judgment. This paper, first, presents the Gesellschaft für Anlagen und Reaktorsicherheit methodology to propagate the uncertainty in thermal-hydraulic macroscopic parameters and, then, shows the results when the methodology is applied to a PWR reactor.

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References

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