Requirements and approaches to BN-1200 safety provision
Creators
- 1. JSC "OKBM Afrikantov", Nizhny Novgorod (Russian Federation)
- 2. FSUE "SSC RF-IPPE named after A. I. Leypunsky" , Obninsk (Russian Federation)
Description
BN-1200 design should meet the following safety requirements: • Current regulatory safety requirements for operating nuclear power plants; • Core damage frequency should not exceed 10-6 1/reactor·year; • Large early release frequency should not exceed 10-7 1/reactor·year; • Elimination of accidents with consequences requiring the need for offsite public evacuation. In any technically credible situation, the following requirements must be implemented: • Removal of decay heat generated by the reactor while maintaining its structural integrity; • Localization of the majority of radioactive products escaping from the reactor in the event of potential accidents within a special above-reactor premise; • The reactor should go subcritical while maintaining acceptable temperature conditions of its components. Implementation of all of these requirements should ensure achievement of the objective of precluding offsite public evacuation
Files
49059911.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
- 16 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
- 49059911
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BN-1200 REACTOR; DAMAGE; LOSS OF COOLANT; NUCLEAR POWER PLANTS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; REACTOR DESIGN; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SAFETY CULTURE; SCRAM
- Descriptors DEC
- ACCIDENTS; ATTITUDES; BEYOND-DESIGN-BASIS ACCIDENTS; BREEDER REACTORS; COOLING SYSTEMS; DESIGN; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR SHUTDOWN; REACTORS; REMOVAL; SAFETY; SEVERE ACCIDENTS; SHUTDOWN; SODIUM COOLED REACTORS; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- IAEA--622-I3-TM-47191