Research on thermal hydraulic behavior of small-break LOCAs in AP1000
Article Properties
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LanguageEnglish
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DOI (url)
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Publication Date2013/10/01
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Journal
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Indian UGC (journal)
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Refrences59
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Citations21
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W.W. Wang
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G.H. Su
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W.X. Tian
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S.Z. Qiu
Cite
Wang, W.W., et al. “Research on Thermal Hydraulic Behavior of Small-Break LOCAs in AP1000”. Nuclear Engineering and Design, vol. 263, 2013, pp. 380-94, https://doi.org/10.1016/j.nucengdes.2013.06.004.
Wang, W., Su, G., Tian, W., & Qiu, S. (2013). Research on thermal hydraulic behavior of small-break LOCAs in AP1000. Nuclear Engineering and Design, 263, 380-394. https://doi.org/10.1016/j.nucengdes.2013.06.004
Wang, W.W., G.H. Su, W.X. Tian, and S.Z. Qiu. “Research on Thermal Hydraulic Behavior of Small-Break LOCAs in AP1000”. Nuclear Engineering and Design 263 (2013): 380-94. https://doi.org/10.1016/j.nucengdes.2013.06.004.
Wang W, Su G, Tian W, Qiu S. Research on thermal hydraulic behavior of small-break LOCAs in AP1000. Nuclear Engineering and Design. 2013;263:380-94.
Journal Categories
Technology
Electrical engineering
Electronics
Nuclear engineering
Technology
Electrical engineering
Electronics
Nuclear engineering
Nuclear engineering
Atomic power
Technology
Engineering (General)
Civil engineering (General)
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Refrences
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| Simulated AP1000 response to design basis small-break LOCA events in APEX-1000 test facility | Nuclear Engineering and Technology |
| 2007 | |
| IIST small break LOCA experiments with passive core cooling injection | Nuclear Engineering and Design |
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| Experimental study on the performance of the passive safety injection in an IIST | Nuclear Technology |
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Citations
| Title | Journal | Journal Categories | Citations | Publication Date |
|---|---|---|---|---|
| Multi-physics analysis of SBLOCA by coupled Neutronics/Thermal-Hydraulics full plant model | Nuclear Engineering and Design |
| 2024 | |
| Experimental study on surface characteristics and thermal conductivity of new zirconium alloy with oxide layer | Progress in Nuclear Energy |
| 1 | 2022 |
Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code | Kerntechnik |
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The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses | Kerntechnik |
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| Computational analysis of gas–liquid flow in an idealised CANDU reactor header under conditions that are relevant to small-break loss-of-coolant and loss-of-flow accidents | Nuclear Engineering and Design |
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Citations Analysis
The category
Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power 20
is the most commonly referenced area in studies that cite this article. The first research to cite this article was titled 10.1016/j.pnucene.2013.08.002 and was published in 2014. The most recent citation comes from a 2024 study titled Multi-physics analysis of SBLOCA by coupled Neutronics/Thermal-Hydraulics full plant model. This article reached its peak citation in 2022, with 3 citations. It has been cited in 8 different journals, 25% of which are open access. Among related journals, the Progress in Nuclear Energy cited this research the most, with 6 citations. The chart below illustrates the annual citation trends for this article.