Analysis of Safety Margins in an Initial Stage during the KALIMER Station Blackout
Description
The main effort in the present study contributes to investigating the safety margins by analyzing the KALIMER station blackout accident. Natural circulation becomes the main heat transfer mechanism. The flow depends mostly on pump's halving time, friction factor for the wire-wrapped rod bundles in the core, and heat transfer coefficient. Therefore, physical models concerned with heat transfer in both pipe internals (IHX/DHX tube sides) and tube bundles (core, IHX/DHX shell sides), including the core wire-wrapped rod bundles, are also to be assessed in the study. In results, the heat transfer coefficient currently featured in SSC-K for an IHX rod bundle has been found acceptable. The heat transfer coefficient used for the core rod bundle, however, has not shown suitability and thus an alternative one has been proposed. Meanwhile, the friction factor model in SSC-K has not shown a prominent discrepancy in prediction trend but it has not been backed by an enough theoretical basis so that it has been replaced by the Cheng and Todreas model. An assessment matrix has been made to analyze systematically the effects of those parameters affecting on the conservatism of the safety analysis, and the matrix is constituted with the average value and the upper/lower limits in the correlation's applicable ranges. The preliminary calculation has shown negligible effect on the fuel temperature, while the pump halving time and the friction factor for the wire-wrapped rod bundle in the core have affected on the analysis results
Availability note (English)
Available from INIS in electronic form; Also available from KAERIFiles
39121523.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 92 p.
- Report number
- KAERI/TR--3527/2008
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 39121523
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENTS; FRICTION FACTOR; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; OUTAGES; SAFETY ANALYSIS; SAFETY MARGINS
- Descriptors DEC
- DIMENSIONLESS NUMBERS; ENERGY TRANSFER; FUEL ASSEMBLIES; REACTORS
Optional Information
- Notes
- 35 refs, 54 figs, 1 tab