Calculation of core safety parameters and uncertainty analyses during unprotected transients for the ALLEGRO and a sodium-cooled fast reactor

Author:

Batki Bálint,Keresztúri András,Panka István

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs;Buiron,2015

2. European Commission – 7th Framework Programme: the Collaborative Project on European Sodium Fast Reactor (CP ESFR);Fiorini;Nucl. Eng. Des.,2011

3. Gadó, J., Belovsky, L., Hatala, B., Vasile, A., Wrochna, G., 2017. The ALLEGRO experimental gas-cooled fast reactor project. In: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg.

4. GRS method for uncertainty and sensitivity evaluation of code results and applications;Glaeser;Sci. Technol. Nucl. Installations,2008

5. Glaser, H., Bazin, P., Baccou, J., Chojnacki, E., Dectercke, S., 2011. BEMUSE phase VI report: status report of the area, classification of the methods, conclusions and recommendations. NEA.

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