Published 2014
| Version v1
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Safety Design Approach for the Development of Prototype Gen-IV SFR
Description
• Emphasize accident prevention rather than mitigation. • Maximize utilization of inherent and passive safety features. • Ensure early termination of accident without core damage for all design basis and beyond-design-basis accidents. • Demonstrate in-vessel retention and coolable geometry of molten core for events in the residual risk category. • Ensure containment of radioactive material even in case of multiple low-probability initiating events.
Files
49059910.pdf
Files
(1.7 MB)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- Fourth Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 25 p.
- Report number
- INIS-XA--18K5269
Conference
- Title
- 4. Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors
- Dates
- 10-11 Jun 2014
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49059910
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BEYOND-DESIGN-BASIS ACCIDENTS; BRAYTON CYCLE; FAST REACTORS; LIQUID METAL FUELS; REACTOR DESIGN; REACTOR SAFETY; SAFETY ANALYSIS; SCRAM; SODIUM COOLED REACTORS; VOID COEFFICIENT
- Descriptors DEC
- ACCIDENTS; DESIGN; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; LIQUID FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; NUCLEAR FUELS; REACTIVITY COEFFICIENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTOR SHUTDOWN; REACTORS; REMOVAL; SAFETY; SHUTDOWN; THERMODYNAMIC CYCLES
Optional Information
- Secondary number(s)
- IAEA--622-I3-TM-47191