Published 1989
| Version v1
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NPP Krsko containment environmental conditions during postulated accident
Description
This paper presents NPP Krsko containment pressure and temperature increase during Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB). Containment environmental condition calculation was performed by CONTEMPT4/MOD4 computer code. Design accident calculations were performed by RELAP4/MOD6 and RELAP5/MOD1 computer codes. Calculational abilities and application methodology of these codes are presented. The CONTEMPT code is described in more detail. The containment pressure and temperature time distribution are presented as well. (author)
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCAFiles
38011906.pdf
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Additional details
Additional titles
- Original title (Croatian)
- Ambijentalni uvjeti u kontejnmentu NE Krsko pri projektnim kvarovima
Publishing Information
- Publisher
- Society for Electronics,Telecommunications, Computers, Automation, and Nuclear Engineering
- Imprint Place
- Belgrade (Yugoslavia)
- Imprint Pagination
- 8 p.
- Report number
- INIS-RS--0510
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
- 38011906
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; DESIGN BASIS ACCIDENTS; ENVIRONMENTAL EFFECTS; KRSKO REACTOR; LOSS OF COOLANT; LOSS OF FLOW; PRESSURE DEPENDENCE; R CODES; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs., 4 figs.