Published 1988
| Version v1
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Determining the boron concentration during long-term cooling of the reactor core after large loss of coolant accident
Description
Critical boron concentration before and after postulated loss of coolant accident with long-term cooling recirculation was calculated for cycle 6 of Krsko NPP. The limiting boron concentration curve of containment sump was calculated for equilibrium conditions. The results were analysed and showed that the boron concentration in refueling water storage tank and in safety injection accumulators should be increased from 2000 to 2100 ppm in 6th cycle. In the consequence corresponding chapters of the NPP Krsko technical Specifications were changed as well. (author)
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCAFiles
38013853.pdf
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Additional details
Additional titles
- Original title (Slovenian)
- Dolocenje koncentracij bora pri dolgotrajnoem hladjenju sredice po veliki izlivni nezgodi
Publishing Information
- Publisher
- Society for Electronics,Telecommunications, Automation, and Nuclear Engineering
- Imprint Place
- Belgrade (Yugoslavia)
- Imprint Pagination
- 8 p.
- Report number
- INIS-RS--0558
Conference
- Title
- Society for Electronics, Telecommunications, Computers, Automation, and Nuclear Engineering
- Original Conference Title
- ETAN '88: 32. Konferencija za elektroniku, telekomunikacije, automatiku i nuklearnu tehniku
- Acronym
- 32. Conference - ETRAN '88
- Dates
- 6-10 Jun 1988
- Place
- Sarajevo (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Serbia
- INIS RN
- 38013853
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON; CONCENTRATION RATIO; CONTAINMENT; DESIGN BASIS ACCIDENTS; FUEL CYCLE; KRSKO REACTOR; LOSS OF COOLANT; SAFETY INJECTION
- Descriptors DEC
- ACCIDENTS; DIMENSIONLESS NUMBERS; ELEMENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SEMIMETALS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 2 tabs., 1 figs.