Modeling of AP1000 and simulation of 10-inch cold leg small break LOCA using the CESAR thermal-hydraulic module of ASTEC

Giuli, M. Di; Sumini, Marco; Rosa, F. De

doi:10.1016/j.pnucene.2015.04.012

Cited by 4 publications

(1 citation statement)

References 5 publications

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“…Wang et al simulated and analyzed cold leg (CL) small-break LOCAs for AP1000 using RELAP5/MOD3.4 codes, including 2-inch, 4-inch, and 8-inch breaks, and the peak cladding temperatures during the process could meet the safety criterion [14][15][16][17]. Di Giuli et al modeled all the PCCS for the AP1000 and studied a 10-inch small-break LOCA scenario using CESAR codes; when compared to the Westinghouse-developed NOTRUMP code as reference showing a reasonable agreement [18]. Quan et al conducted long-term IRWST injection core cooling study under AP1000 and CAP1400 SBLOCA scenario by the 1-D thermal-hydraulic analytical model.…”

Section: Introductionmentioning

confidence: 99%

RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China

Sun

Wang

et al. 2020

Science and Technology of Nuclear Installations

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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.

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