Design Evolutions of the Molten Salt Fast Reactor
- 1. LPSC-IN2P3-CNRS - Université Grenoble Alpes, Grenoble (France)
Description
CNRS has focused R&D efforts on the development of a new reactor concept called the Molten Salt Fast Reactor (MSFR), characterized by a circulating liquid fuel and a fast neutron spectrum. This paper presents the new design proposed for the fuel circuit in the frame of the SAMOFAR European project and focuses on the design studies of the emergency draining system of the MSFR. These new designs result from physical and preliminary safety studies such as optimizing the use of the molten salt both as fuel and coolant, defining the operating procedures or minimizing the fuel leakage risks. Additional requirements are considered for the emergency draining system to be able to confine the fuel and to evacuate the residual heat over very long time periods (months) with no human intervention and to guaranty that under no circumstance the salt may reach criticality in this area. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108618-1
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 10 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51006377
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; DESIGN; FAST NEUTRONS; FAST REACTORS; LIQUID FUELS; MOLTEN SALT COOLED REACTORS; NEUTRON SPECTRA; SAFETY
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; EPITHERMAL REACTORS; FERMIONS; FUELS; HADRONS; MOLTEN SALT REACTORS; NEUTRONS; NUCLEONS; REACTORS; SPECTRA
Optional Information
- Notes
- 5 refs., 10 figs., 1 tab.
- Secondary number(s)
- IAEA-CN--245-575