Abstract
Qinshan nuclear power plant is the first large Chinese-designed nuclear power station based on pressurized water reactor, and the second generation main stream active safety injection system is adopted for Qinshan nuclear power plant. In this paper, a novel passive safety injection system (PSIS) has been proposed for ocean-based Qinshan Phase One nuclear power plant to replace the original active one. The PSIS contains high-pressure, medium-pressure, and lower-pressure safety injection systems, and a two-stage automatic depressurization system. To evaluate the system performance, small-break LOCA has been investigated using RELAP5. Various break sizes and locations including 2-inch, 10-inch cold leg break, and double-ended direct vessel injection line break were analyzed. Key safety parameters such as safe injection mass flow rates, coolant level of the core, system pressure, and fuel cladding temperature were monitored during the accident process. The results illustrate that the performance of the safety injection system can guarantee the effective core cooling and submerged under different LOCA even with only half of the safety injection system, which can fulfill the single failure criteria. The thermal-hydraulic analysis for the Qinshan passive safety injection system is significant to master the related technologies for Chinese engineer and develop the Chinese-designed third-generation nuclear power plants, and the PSIS can guarantee the reactor submerged under LOCA even plus the station block out accident.
Highlights
Nuclear safety is an extremely important issue for nuclear energy application, especially after the occurrence of Fukushima Dai-ichi nuclear disaster in 2011, after when people become more concerned about the risk of nuclear power [1]
One of the options in the Chinese Offshore Nuclear Power Plant (ONPP) technology roadmap is to compress the mature and reliable Qinshan Phase One loop-type pressurized water reactor (PWR) into compact size. e loop-type PWR will be placed in a gravitybased structure (GBS) that is made of steel reinforced concrete [5]
When compared with ACME integral test data including 2-inch and double-ended direct vessel injection (DVI) breaks of various boundary conditions, the results showed a good agreement [19, 20]
Summary
Nuclear safety is an extremely important issue for nuclear energy application, especially after the occurrence of Fukushima Dai-ichi nuclear disaster in 2011, after when people become more concerned about the risk of nuclear power [1]. One solution to improve the safety performance under accident conditions is passive safety system application for nuclear power plants (NPPs). Another potential solution for using nuclear energy safely is moving the traditional NPP from lands to ocean to take advantage of infinite cooling source, sea water. This concept of NPP is called Offshore Nuclear Power Plant (ONPP) [2,3,4]. One of the options in the Chinese ONPP technology roadmap is to compress the mature and reliable Qinshan Phase One loop-type pressurized water reactor (PWR) into compact size.
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