Uncertainty and Sensitivity of Neutron Kinetic Parameters in the Dynamic Response of a PWR Rod Ejection Accident Coupled SimulationReport as inadecuate

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Science and Technology of Nuclear InstallationsVolume 2012 2012, Article ID 625878, 10 pages

Research Article

Institute for the Industrial, Radiophysical and Environmental Safety ISIRYM, Universitat Politècnica de València, 46022 Valencia, Spain

Applied Statistics, Operations Research and Quality Department, Universitat Politècnica de València UPV, Cami de Vera, s-n, 46022 Valencia, Spain

Lehrstuhl für Nukleartechnik, Technische Universität München TUM, Boltzmannstraße 15, 85747 Garching, Germany

Received 21 August 2012; Revised 24 October 2012; Accepted 12 November 2012

Academic Editor: Oscar Cabellos

Copyright © 2012 C. Mesado et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


In nuclear safety analysis, it is very important to be able to simulate the different transients that can occur in a nuclear power plant with a very high accuracy. Although the best estimate codes can simulate the transients and provide realistic system responses, the use of nonexact models, together with assumptions and estimations, is a source of uncertainties which must be properly evaluated. This paper describes a Rod Ejection Accident REA simulated using the coupled code RELAP5-PARCSv2.7 with a perturbation on the cross-sectional sets in order to determine the uncertainties in the macroscopic neutronic information. The procedure to perform the uncertainty and sensitivity U&S analysis is a sampling-based method which is easy to implement and allows different procedures for the sensitivity analyses despite its high computational time. DAKOTA-Jaguar software package is the selected toolkit for the U&S analysis presented in this paper. The size of the sampling is determined by applying the Wilks’ formula for double tolerance limits with a 95% of uncertainty and with 95% of statistical confidence for the output variables. Each sample has a corresponding set of perturbations that will modify the cross-sectional sets used by PARCS. Finally, the intervals of tolerance of the output variables will be obtained by the use of nonparametric statistical methods.

Author: C. Mesado, A. Soler, T. Barrachina, R. Miró, J. C. García-Díaz, R. Macián-Juan, and G. Verdú

Source: https://www.hindawi.com/


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