TAILIEUCHUNG - Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

This paper describes the neutronic benchmarks and the results obtained by the various participants of the FP7 project EVOL and the ROSATOM project MARS. The aim of the benchmarks was two-fold: first to verify and validate each of the code packages of the project partners, adapted for liquid-fueled reactors, and second to check the dependence of the core characteristics to nuclear data set for application on a molten salt fast reactor (MSFR). | Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects EPJ Nuclear Sci. Technol. 5 2 2019 Nuclear Sciences M. Brovchenko et al. published by EDP Sciences 2019 amp Technologies https epjn 2018052 Available online at https REGULAR ARTICLE Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects Mariya Brovchenko1 Jan-Leen Kloosterman2 Lelio Luzzi3 Elsa Merle1 Daniel Heuer1 Axel Laureau1 Olga Feynberg4 Victor Ignatiev4 Manuele Aufiero3 Antonio Cammi3 Carlo Fiorina3 Fabio Alcaro5 Sandra Dulla5 Piero Ravetto5 Lodewijk Frima2 Danny Lathouwers2 and Bruno Merk6 1 CNRS-IN2P3-LPSC Université Grenoble Alpes Grenoble France 2 TU Delft Delft The Netherlands 3 Politecnico di Milano Milano Italy 4 Kurchatov Institute Moscow Russia 5 Politecnico di Torino Torino Italy 6 Helmholtz-Zentrum Dresden Rossendorf Dresden Germany Received 30 August 2018 Received in final form 23 October 2018 Accepted 17 December 2018 Abstract. This paper describes the neutronic benchmarks and the results obtained by the various participants of the FP7 project EVOL and the ROSATOM project MARS. The aim of the benchmarks was two-fold first to verify and validate each of the code packages of the project partners adapted for liquid-fueled reactors and second to check the dependence of the core characteristics to nuclear data set for application on a molten salt fast reactor MSFR . The MSFR operates with the thorium fuel cycle and can be started with 233U-enriched U and or TRU elements as initial fissile load. All three compositions were covered by the present benchmark. The calculations have confirmed that the MSFR has very favorable characteristics not present in other Gen4 fast reactors like strong negative temperature and void reactivity coefficients a low-fissile inventory a reduced long- lived waste production and its burning capacities of nuclear waste produced in currently

• Năng lượng
• FP7 project EVOL
• ROSATOM project MARS
• Liquid fueled reactor
• Molten salt fast reactor
• Nuclear data set
• Bayesian set of equation
• Random nuclear data
• Nuclear data correlation
• Bigten criticality benchmark
• Bayesian Monte Carlo method