France Proposal of Applied Generation IV SFR Safety Design Criteria
- 1. CEA, Paris (France)
- 2. EDF, Paris (France)
- 3. Areva, Paris (France)
Description
The following criteria is only a proposal to initiation discussion. Currently appplied to the ASTRID project: The reactor core shall be self-stable for normal operation, with its three reactivity coefficients of flow-rate, temperature and power feedback to be negative. 2. The existence of two diversified automatic shutdown systems shall be complemented by a third independent and passive shutdown level that do not rely on active detection and control systems. 3. In case where automatic shutdown systems are not activated by the control process during any of the design accident conditions, the core shall not melt down on the short term, and sufficient time shall be available before any collapse of the reactor structures. 4. In case of inadvertent withdrawal of one or more control rod, demonstrate that there is no partial melting of a sub-assembly. 5. Demonstrate that a credible flow of gas or fluid that can vaporize, like oil, through the core is not sensitive on the core reactivity. 6. In case of a loss of decay heat removal systems, connections to link additional external systems shall be available. 7. Structures that are important for safety, of the main vessel, the safety vessel, their support and the core support structures shall be periodically inspected.
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49059906.pdf
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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
- 8 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
- 49059906
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CONTROL ELEMENTS; FAST REACTORS; FLOW RATE; FRANCE; MELTING; REACTIVITY COEFFICIENTS; REACTOR ACCIDENT SIMULATION; REACTOR CONTROL SYSTEMS; REACTOR CORES; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS; SODIUM COOLED REACTORS; STEADY-STATE CONDITIONS
- Descriptors DEC
- CONTROL SYSTEMS; DEVELOPED COUNTRIES; EPITHERMAL REACTORS; EUROPE; LIQUID METAL COOLED REACTORS; PHASE TRANSFORMATIONS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; SIMULATION; WESTERN EUROPE
Optional Information
- Secondary number(s)
- IAEA--622-I3-TM-47191