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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.8
- 수록면
- 1,626 - 1,637 (12page)
- DOI
- 10.1016/j.net.2020.01.010
이용수
초록· 키워드
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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 multiphysics (coupled) and multi-scale simulations. The Gesellschaft fur 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 ewhich data is obtained from a real PWR teste 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 fur Anlagen und Reaktorsicherheit methodology to propagate the uncertainty in thermalhydraulic macroscopic parameters and, then, shows the results when the methodology is applied to a PWR reactor
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참고문헌 (22)
참고문헌 신청
K. Ivanov / 2013 / Benchmarks for Uncertainty Analysis in Modelling (UAM) for the Design, Operation and Safety Analysis of LWRs-Volume I: Specification and Support Data for Neutronics Cases (Phase I)
M. Avramova / 2009 / Uncertainty analysis of COBRA-TF void distribution predictions for the OECD/NRC BFBT Benchmark / Proceedings of the International Conference on advances in mathematics, computational methods, and reactor physics (M&C’09)
C. Mesado / 2012 / Uncertainty and sensitivity of neutron kinetic parameters in the dynamic response of a PWR rod ejection accident coupled simulation / Sci. Technol. Nucl. Install
A. Hernandez-Solís / 2012 / Uncertainty and Sensitivity Analysis Applied to LWR Neutronic and Thermal-Hydraulic Calculations
G. Strydom / 2013 / Uncertainty and sensitivity analyses of a pebble bed HTGR loss of cooling event / Sci. Technol. Nucl. Install
M. Avramova / 2009 / Uncertainty analysis of COBRA-TF void distribution predictions for the OECD/NRC BFBT Benchmark / Proceedings of the International Conference on advances in mathematics, computational methods, and reactor physics (M&C’09)
C. Mesado / 2012 / Uncertainty and sensitivity of neutron kinetic parameters in the dynamic response of a PWR rod ejection accident coupled simulation / Sci. Technol. Nucl. Install
A. Hernandez-Solís / 2012 / Uncertainty and Sensitivity Analysis Applied to LWR Neutronic and Thermal-Hydraulic Calculations
G. Strydom / 2013 / Uncertainty and sensitivity analyses of a pebble bed HTGR loss of cooling event / Sci. Technol. Nucl. Install
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