TAILIEUCHUNG - Preliminary proliferation study of the molten salt fast reactor

This paper has the main objective of presenting some proliferation challenges for the reference version of the Molten Salt Fast Reactor (MSFR), a large power reactor based on the thorium fuel cycle. | Preliminary proliferation study of the molten salt fast reactor EPJ Nuclear Sci. Technol. 6 5 2020 Nuclear Sciences M. Allibert et al. published by EDP Sciences 2020 amp Technologies https epjn 2019062 Available online at https REGULAR ARTICLE Preliminary proliferation study of the molten salt fast reactor Michel Allibert1 Elsa Merle1 Sylvie Delpech2 Delphine Gerardin1 Daniel Heuer1 Axel Laureau1 and Simon Moreau1 1 CNRS IN2P3 LPSC UGA Grenoble INP Grenoble France 2 CNRS IN2P3 IPN Orsay Orsay France Received 15 March 2019 Received in final form 17 September 2019 Accepted 12 December 2019 Abstract. The molten salt reactor designs where fissile and fertile materials are dissolved in molten salts under consideration in the framework of the Generation IV International Forum present some unusual characteristics in terms of design operation safety and also proliferation resistance issues. This paper has the main objective of presenting some proliferation challenges for the reference version of the Molten Salt Fast Reactor MSFR a large power reactor based on the thorium fuel cycle. Preliminary studies of proliferation resistance are presented here dedicated to the threat of nuclear material diversion in the MSFR considering both the reactor system itself and the processing units located onsite. 1 Introduction By applying the GIF methodology to this case we successively identify the elements of the nuclear power The Generation IV International Forum GIF 1 has plant NPP site we identify the targets for material proposed a methodology that should allow the analysis of diversion and the pathways to achieve diversion and we proliferation resistance and physical protection PR amp PP suggest countermeasures to prevent this. This corre- issues in advanced nuclear reactors under development. An sponds to the designer s work and do not contain risks initial application of this methodology to the MSFR 2 is evaluation. presented here including an .

• Năng lượng
• Molten Salt Fast Reactor
• Large power reactor
• Thorium fuel cycle
• Generation IV International Forum
• Proliferation resistance and physical protection
• Nuclear engineering and technology
• Methodology for the identification
• The postulated initiating events of the Molten Salt Fast Reactor
• Fast neutron spectrum
• Technological neutral methodologies
• The LoD tool
• Horizon2020 program SAMOFAR
• Safety Assessment of the Molten Salt Fast Reactor
• Lines of Defence
• Low carbon electricity production
• FP7 project EVOL
• ROSATOM project MARS
• Liquid fueled reactor
• Nuclear data set
• Primary heat exchanger
• Heat exchanger design
• 3D CFD analyses
• ANSYS Fluent commercial code
• Control oriented plant dynamics tool
• Standard control transient
• Control oriented power plant simulator
• Analytical steady state 2 D model
• Nuclear energy
• Proper orthogonal decomposition
• Data driven
• Uncertainty and sensitivity analysis
• Transient analysis
• Parametrized multiphysics computations
• Molten salt fast reactor concept
• OpenFOAM based multiphysics solver
• Latin hypercube sampling algorithm