Title: Uncertainty and sensitivity analysis of fission gas behavior calculations in engineering-scale fuel modeling
Citation: JOURNAL OF NUCLEAR MATERIALS vol. 456 p. 398 - 408
Publication Year: 2015
JRC N°: JRC88588
ISSN: 0022-3115
URI: http://www.sciencedirect.com/science/article/pii/S0022311514006771
DOI: 10.1016/j.jnucmat.2014.09.077
Type: Articles in periodicals and books
Abstract: The role of intrinsic uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel performance code and a recently implemented physics-based model for the coupled ssion gas release and swelling. Through the integration of BISON with the DAKOTA software, a sensitivity analysis of the results to selected model parameters is carried out based on UO2 single-pellet simulations covering different powerregimes. The parameters are varied within ranges representative of the relative uncertainties and consistent with the information from the open literature. The study leads to an initial quantitative assessment of the uncertainty in fission gas behavior modeling with the parameter characterization presently available. Also, the relative importance of the single parameters is evaluated. Moreover, a sensitivity analysis is carried out based on simulations of a fuel rod irradiation experiment, pointing out a signicant impact of the considered uncertainties on the calculated ssion gas release and cladding diametral strain. The results of the study indicate that the commonly accepted deviation between calculated and measured fission gas release by a factor of 2 approximately corresponds to the inherent modeling uncertainty at high ssion gas release. Nevertheless, higher deviations may be expected for values around 10% and lower. Implications are discussed in terms of directions of research for the improved modeling of ssion gas behavior for engineering purposes.
JRC Directorate:Nuclear Safety and Security

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