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Usually, simulation tools are validated on experimental data considering a Best Estimate simulation case and there is no quantification of this validation, which remains based on a rough expert judgment. This paper presents an advanced validation treatment of the simulation tool OCARINa, devoted to Unprotected Transient OverPower (UTOP) accidents, on two CABRI tests, considering this time, a Best Estimate Plus Uncertainties (BEPU) approach. The output results of interest are both scalar physical data such as the time and location of the pin failure and associated molten mass and vector data such as temperature axial distribution or temperature evolution versus time. This approach is a first step in quantifying the degree of agreement between the calculation results and the experimental results. It is of great interest for the VV&UQ (Verification, Validation and Uncertainty Quantification) approach, which leads to the qualification of scientific calculation tools.Within the framework of the Generation IV SFR R&D project in which the CEA is involved, OCARINa is a physical tool, relevant for performing pre-conceptual design studies, devoted to simulation of UTOP accidents on heterogeneous cores. Such accidents could not be simulated with mechanistic calculation tools such as SAS4A or SIMMER with their current capabilities; the thermomechanical models are not finalized in SIMMER tool and the SAS4A tool is only validated for homogeneous cores. The final objective aims at deriving the variability of the main results of interest to quantify the safety margins.The final use of the OCARINa tool being to perform sensitivity studies on the various possible sodium fast nuclear pre-conceptual core designs, the validation of this tool is first discussed at the pin scale (where separate effect test measurements are available) based on statistical treatment. This enables to determine the lacks and uncertainties of this tool. The modeling is then extended from local pin behavior to global core behavior adding a point kinetic neutronic model. Final simulations of UTOP accidents caused by a uniform space reactivity ramp on an SFR (Sodium-cooled Fast Reactor) core are realized taking into account the specificities of the pins of the various assemblies. The orders of magnitude of mechanical energy released are derived.
Usually, simulation tools are validated on experimental data considering a Best Estimate simulation case and there is no quantification of this validation, which remains based on a rough expert judgment. This paper presents an advanced validation treatment of the simulation tool OCARINa, devoted to Unprotected Transient OverPower (UTOP) accidents, on two CABRI tests, considering this time, a Best Estimate Plus Uncertainties (BEPU) approach. The output results of interest are both scalar physical data such as the time and location of the pin failure and associated molten mass and vector data such as temperature axial distribution or temperature evolution versus time. This approach is a first step in quantifying the degree of agreement between the calculation results and the experimental results. It is of great interest for the VV&UQ (Verification, Validation and Uncertainty Quantification) approach, which leads to the qualification of scientific calculation tools.Within the framework of the Generation IV SFR R&D project in which the CEA is involved, OCARINa is a physical tool, relevant for performing pre-conceptual design studies, devoted to simulation of UTOP accidents on heterogeneous cores. Such accidents could not be simulated with mechanistic calculation tools such as SAS4A or SIMMER with their current capabilities; the thermomechanical models are not finalized in SIMMER tool and the SAS4A tool is only validated for homogeneous cores. The final objective aims at deriving the variability of the main results of interest to quantify the safety margins.The final use of the OCARINa tool being to perform sensitivity studies on the various possible sodium fast nuclear pre-conceptual core designs, the validation of this tool is first discussed at the pin scale (where separate effect test measurements are available) based on statistical treatment. This enables to determine the lacks and uncertainties of this tool. The modeling is then extended from local pin behavior to global core behavior adding a point kinetic neutronic model. Final simulations of UTOP accidents caused by a uniform space reactivity ramp on an SFR (Sodium-cooled Fast Reactor) core are realized taking into account the specificities of the pins of the various assemblies. The orders of magnitude of mechanical energy released are derived.
This paper presents a statistical methodology for a quantified validation of the OCARINa simulation tool, which models the unprotected transient overpower (UTOP) accidents. This validation on CABRI experiments is based on a best-estimate plus uncertainties (BEPU) approach. To achieve this, a general methodology based on recent statistical techniques is developed. In particular, a method for the quantification of multivariate data is applied for the visualization of simulator outputs and their comparison with experiments. Still for validation purposes, a probabilistic indicator is proposed to quantify the degree of agreement between the simulator OCARINa and the experiments, taking into account both experimental uncertainties and those on OCARINa inputs. Going beyond a qualitative validation, this work is of great interest for the verification, validation and uncertainty quantification or evaluation model development and assessment process approaches, which leads to the qualification of scientific calculation tools. Finally, for an in-depth analysis of the influence of uncertain parameters, a sensitivity analysis based on recent dependence measures is also performed. The usefulness of the statistical methodology is demonstrated on CABRI-E7 and CABRI-E12 tests. For each case, the BEPU propagation study is carried out performing 1000 Monte Carlo simulations with the OCARINa tool, with nine uncertain input parameters. The validation indicators provide a quantitative conclusion on the validation of the OCARINa tool on both transients and highlight future efforts to strengthen the demonstration of validation of safety tools. The sensitivity analysis improves the understanding of the OCARINa tool and the underlying UTOP scenario.
This dissertation has been submitted in partial fulfillment of requirements for an advanced degree at The University of Arizona and is deposited in the University Library to be made available to borrowers under rules of the Library. Brief quotations from this dissertation are allowable without special permission, provided that accurate acknowledgment of source is made. Requests for permission for extended quotation from or reproduction of this manuscript in whole or in part may be granted by the head of the major department or the Dean of the Graduate College when in his judgment the proposed use of the material is in the interests of scholarship. In all other instances, however, permission must be obtained from the author. SIGNED , /LjL-ACKNOWLEDGMENTS I would like to express my sincere gratitude to Dr. Richard L. Brehm for his great assistance over the years, culminating in his direction of this work. I am also extremely grateful to the Department of Nuclear Engineering, The University of Arizona, and the United States Atomic Energy Commission for the award of an AEC traineeship during 'three years of my graduate study.
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