Published 2010 | Version v1
Miscellaneous Open

SFR safety design concept and related safety R&D in China

Creators

  • 1. China Institute of Atomic Energy (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

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Part of:
First Joint IAEA-GIF Workshop on Operational and Safety Aspects of Sodium Cooled Fast Reactors. Presentations

Additional details

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

Optional Information