SFR safety design concept and related safety R&D in China
Description
Defense in depth safety design in CEFR: CEFR functions are designed according to the defense in depth principle, which provide a series of multiple layers of defenses. Level 1 defense, is to protect from deviating from normal operation and system failure, by providing a correct and conservative design, construction, maintenance and operation of the nuclear power plant. • Level 2 defense, is to detect and correct deviation from normal operation, to protect anticipation operational events from escalating to accident conditions, by designing certain special systems, i.e. reliable shutdown system, reactivity control system, various protection system and monitoring and detecting system, and developing operating procedures. Level 3 defense, is to ensure reactor shutdown safely, maintain a safe and steady shutdown state and maintain at least one radioactivity barrier intact provided that design basis accidents occur, by designing and equipping engineered safety systems and inherent safety design. • Level 4 defense, is to ensure radioactivity release are remained as possible as practically low for severe accidents which already likely are beyond design basis, by developing accident management procedures. The most important goal is to protect confinement function. • Level 5 defense, is to mitigate radioactivity consequences caused by potential radioactive materials from accident conditions, by equipping appropriate equipments in the emergency control centre and developing in site/off site emergency response plan.
Files
49104086.pdf
Files
(782.5 kB)
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Additional details
Identifiers
- URL
- https://www-legacy.iaea.org/INPRO/cooperation/IAEA-GIF<sub>W</sub>S<sub>o</sub>n<sub>S</sub>FRs/20SFR<sub>s</sub>afety<sub>d</sub>esign<sub>c</sub>oncept<sub>a</sub>nd<sub>r</sub>elated<sub>s</sub>afety<sub>R</sub>& D.pdf; https://www-legacy.iaea.org/INPRO/cooperation/IAEA-GIF_WS_on_SFRs/20SFR_safety_design_concept_and_related_safety_R&D.pdf;
Publishing Information
- Imprint Title
- First Joint IAEA-GIF Workshop on Operational and Safety Aspects of Sodium Cooled Fast Reactors. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 19 p.
- Report number
- INIS-XA--18M4855
Conference
- Title
- 1. Joint IAEA-GIF Workshop on Operational and Safety Aspects of Sodium Cooled Fast Reactors
- Dates
- 23-25 Jun 2010
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49104086
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; CONTROL SYSTEMS; DESIGN-BASIS ACCIDENTS; RADIOACTIVE MATERIALS; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR SAFETY; REACTOR SHUTDOWN; SEVERE ACCIDENTS; SODIUM COOLED REACTORS; STEADY-STATE CONDITIONS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; LIQUID METAL COOLED REACTORS; MAINTENANCE; MANAGEMENT; MATERIALS; OPERATION; REACTOR LIFE CYCLE; REACTOR OPERATION; REACTORS; SAFETY; SHUTDOWN