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AbstractAbstract
[en] The Scram power level has significant influence on the steam rate and amount released from the break in main steam pipeline. In order to figure out the safety margin of the containment failure in accident conditions, it is necessary to research and analyze the effects of scram power level on the containment integrity. The thermal-hydraulic model of Passive Containment Cooling System has been built with passive containment analysis code in Large Power Passive Reactor. Based on the basis accident of Main Steam Line Break (MSLB), the containment responses to the different scram power level have been carried out. The analysis results show that: (1) the containment pressure is highest when scram power level is 30% of Fission Power (FP) under keeping the design water film coverage; (2) with decrease of water film coverage, the containment does not fail as a result of overpressure, although the pressure is highest on the scram power level 0%FP; (3) the containment failure could occur without cooling water outside the containment surface on the power level 0%FP. (authors)
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7 figs., 3 tabs., 9 refs.
Record Type
Journal Article
Journal
Chinese Journal of Nuclear Science and Engineering; ISSN 0258-0918; ; v. 38(5); p. 850-854
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