Analysis of uncertainties for results of experiment with boiling-off the coolant simulation using SOCRAT-B1/B2-code for spent fuel pool conditions
Research output: Contribution to journal › Research article › Contributed › peer-review
Contributors
Abstract
The analysis of uncertainties was performed for the significant parameters for conditions with loss of the spent fuel pool cooling using best estimate code SOCRAT-B1/B2. Based on the analysis results, the parameters which have the largest impact on significant results of the calculation are determined. It is also shown that simultaneous deviation of the initial parameters first to the conservative side (for getting maximal cladding temperature at the end of calculation higher so to obtain the worst results in terms of safety) and then to the optimistic side (to obtain the most favorable results in terms of safety) leads to interval of the results larger than the range of uncertainties under consideration. The results of the performed analysis show that this approach can be used for NPP safety justification in accident conditions with loss of spent fuel pool cooling in addition to the methods recommended in regulatory documents.
Details
Original language | English |
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Article number | 112271 |
Number of pages | 112271 |
Journal | Nuclear engineering and design |
Volume | 407 |
Publication status | Published - Jun 2023 |
Peer-reviewed | Yes |
External IDs
Scopus | 85150831661 |
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WOS | 001054213800001 |
Keywords
Subject groups, research areas, subject areas according to Destatis
ASJC Scopus subject areas
Keywords
- Thermal-hydraulics