Status of the ASTRID Project
Description
The ASTRID objections: → Technological demonstration reactor (a step before a First Of A Kind); → Integrating French and international SFRs feedback; → A GEN IV system. Safety: - Level at least equivalent to GEN III systems; - Progresses on Na reactors specificities; - Integrating FUKUSHIMA accident feedback; - Robustness of safety demonstration. Durability: - Need of Fast Breeder Reactors and a closed cycle; - Pu multi recycling to preserve natural resources; - The use of natural depleted uranium in France by FBRs allow producing electricity for few thousands of years. Operability: - Load factor of 80% or more after first "learning" years; - Significant progress concerning In Service Inspection & Repair (ISIR). Ultimate wastes transmutation: - Realization of demonstrations on minor actinides transmutation according to June 28, 2006 French Act on Wastes Management. A mastered investment cost; Non proliferation warranty. → Irradiation services and options test
Files
49059889.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Title
- Fifth Joint IAEA-GIF/INPRO Technical Meeting on Safety of Sodium-Cooled Fast Reactor. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 13 p.
- Report number
- INIS-XA--18K2155
Conference
- Title
- 5. Joint IAEA-GIF/INPRO Workshop on Safety Aspects of Sodium-Cooled Fast Reactors
- Dates
- 23-24 Jun 2015
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49059889
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CLOSED FUEL CYCLE; CONTROL ELEMENTS; CURIE POINT; FBR TYPE REACTORS; FEASIBILITY STUDIES; FRANCE; IN-SERVICE INSPECTION; LIFETIME EXTENSION; MIXED OXIDE FUELS; POOL TYPE REACTORS; REACTOR ACCIDENTS; REACTOR DESIGN; REACTOR SAFETY; RHR SYSTEMS; SEVERE ACCIDENTS; SODIUM; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BEYOND-DESIGN-BASIS ACCIDENTS; BREEDER REACTORS; COOLING SYSTEMS; DESIGN; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; ENERGY SYSTEMS; EPITHERMAL REACTORS; EUROPE; FAST REACTORS; FUEL CYCLE; FUELS; INSPECTION; LIFETIME; LIQUID METAL COOLED REACTORS; MATERIALS; METALS; NUCLEAR FUELS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; REMOVAL; SAFETY; SERVICE LIFE; SOLID FUELS; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Secondary number(s)
- IAEA--622-I3-TM-50169