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http://dx.doi.org/10.1016/j.net.2017.12.007

Uncertainty and sensitivity analysis in reactivity-initiated accident fuel modeling: synthesis of organisation for economic co-operation and development (OECD)/nuclear energy agency (NEA) benchmark on reactivity-initiated accident codes phase-II  

Marchand, Olivier (Institut de Radioprotection et de Surete Nucleaire (IRSN), PSN-RES)
Zhang, Jinzhao (Tractebel (ENGIE))
Cherubini, Marco (Nuclear and Industrial Engineering (NINE))
Publication Information
Nuclear Engineering and Technology / v.50, no.2, 2018 , pp. 280-291 More about this Journal
Abstract
In the framework of OECD/NEA Working Group on Fuel Safety, a RIA fuel-rod-code Benchmark Phase I was organized in 2010-2013. It consisted of four experiments on highly irradiated fuel rodlets tested under different experimental conditions. This benchmark revealed the need to better understand the basic models incorporated in each code for realistic simulation of the complicated integral RIA tests with high burnup fuel rods. A second phase of the benchmark (Phase II) was thus launched early in 2014, which has been organized in two complementary activities: (1) comparison of the results of different simulations on simplified cases in order to provide additional bases for understanding the differences in modelling of the concerned phenomena; (2) assessment of the uncertainty of the results. The present paper provides a summary and conclusions of the second activity of the Benchmark Phase II, which is based on the input uncertainty propagation methodology. The main conclusion is that uncertainties cannot fully explain the difference between the code predictions. Finally, based on the RIA benchmark Phase-I and Phase-II conclusions, some recommendations are made.
Keywords
RIA; Codes Benchmarking; Fuel Modelling; OECD;
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  • Reference
1 NEA/CSNI/R, 6, Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase II, vol. 2, Nuclear Energy Agency, OECD, Paris, France, 2016.
2 NEA/CSNI/R, 1, Reactivity-Initiated Accident Fuel-Rod-Code Benchmark Phase II: Uncertainty and Sensitivity Analyses, Nuclear Energy Agency, OECD, Paris, France, 2017.
3 H. Glaeser, GRS method for uncertainty and sensitivity evaluation of code results and applications, Sci. Technol. Nucl. Install. (2008), 798901.
4 J. Zhang, J. Segurado, C. Schneidesch, Towards an industrial application of statistical uncertainty analysis methods to multi-physical modelling and safety analyses, in: Proc. OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations, Barcelona, Spain, 16-18 November, 2011.
5 E. Gentle, "Monte-Carlo Methods," Encyclopaedia of Statistics, 5, John Wiley and Sons, New-York, 1985, pp. 612-617.
6 NEA/CSNI/R, 4, BEMUSE Phase VI Report - Status Report on the Area, Clas- sification of the Methods, Conclusions and Recommendations, Nuclear Energy Agency, OECD, Paris, France, 2011.
7 NEA/NSC, Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of LWRs, in: Specification and Support Data for the Core Cases (Phase II), vol. II, Nuclear Energy Agency, OECD, Paris, France, 2014, Version 2.0.
8 NEA/CSNI/R, 6, Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase II, vol. 1, Nuclear Energy Agency, OECD, Paris, France, 2016.
9 NEA/CSNI/R, 1, Nuclear Fuel Behaviour Under Reactivity-Initiated Accidents (RIA) Conditions. State of the Art Report, Nuclear Energy Agency, OECD, Paris, France, 2010.
10 NEA/CSNI/R, 7, Nuclear Fuel Behaviour Under Reactivity-Initiated Accidents (RIA) Conditions. Workshop Proceedings, Nuclear Energy Agency, OECD, Paris, France, 2010.
11 NEA/CSNI/R, 7/VOL2, Reactivity Initiated Accident (RIA) Fuel Codes Bench- mark, vol. 2, Nuclear Energy Agency, OECD, Paris, France, 2013.
12 NEA/CSNI/R, 7/VOL1, Reactivity Initiated Accident (RIA) Fuel Codes Bench- mark, vol. 1, Nuclear Energy Agency, OECD, Paris, France, 2013.