Published 1989
| Version v1
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Analysis of the steam generator tube plugging influence to the large break LOCA
Description
The conservative safety analysis of the Large Break Loss of Coolant transient has been performed for 0%, 4% and 10% tubes plugging level. The methodology used followed the requirements of the US NRC. The decrease of the core peaking factor from 2.34 to 2.236 would compensate negative influence of the 10% plugging from the LB LOCA point of view. (author)
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCAFiles
38011904.pdf
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Additional details
Additional titles
- Original title (Slovenian)
- Analiza vpliva ceplenja uparjalnikov na veliko izlivno nezgodo
Publishing Information
- Publisher
- Society for Electronics,Telecommunications, Computers, Automation, and Nuclear Engineering
- Imprint Place
- Belgrade (Yugoslavia)
- Imprint Pagination
- 8 p.
- Report number
- INIS-RS--0508
Conference
- Title
- Society for Electronics, Telecommunications, Computers, Automation, and Nuclear Engineering
- Original Conference Title
- ETAN '89: 33. Konferencija za elektroniku, telekomunikacije, racunarstvo, automatiku i nuklearnu tehniku
- Acronym
- 33. Conference - ETAN '89
- Dates
- 12-17 Jun 1989
- Place
- Novi Sad (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Serbia
- INIS RN
- 38011904
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOSS OF COOLANT; PLUGGING; POWER DENSITY; PWR TYPE REACTORS; REACTOR CORES; SAFETY ANALYSIS; SAFETY STANDARDS; STEAM GENERATORS; TRANSIENTS; TUBES
- Descriptors DEC
- ACCIDENTS; BOILERS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; STANDARDS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 1 tabs., 3 figs.