Large-break LOCA analysis with modified boiling heat-transfer model in TRACE code
Article Properties
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LanguageEnglish
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DOI (url)
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Publication Date2019/05/01
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Journal
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Indian UGC (journal)
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Refrences19
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Citations4
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Riichiro Okawa ORCID (unauthenticated)
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Masahiro Furuya
Cite
Okawa, Riichiro, and Masahiro Furuya. “Large-Break LOCA Analysis With Modified Boiling Heat-Transfer Model in TRACE Code”. Nuclear Engineering and Design, vol. 346, 2019, pp. 97-111, https://doi.org/10.1016/j.nucengdes.2019.03.003.
Okawa, R., & Furuya, M. (2019). Large-break LOCA analysis with modified boiling heat-transfer model in TRACE code. Nuclear Engineering and Design, 346, 97-111. https://doi.org/10.1016/j.nucengdes.2019.03.003
Okawa, Riichiro, and Masahiro Furuya. “Large-Break LOCA Analysis With Modified Boiling Heat-Transfer Model in TRACE Code”. Nuclear Engineering and Design 346 (2019): 97-111. https://doi.org/10.1016/j.nucengdes.2019.03.003.
Okawa R, Furuya M. Large-break LOCA analysis with modified boiling heat-transfer model in TRACE code. Nuclear Engineering and Design. 2019;346:97-111.
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
| Title | Journal | Journal Categories | Citations | Publication Date |
|---|---|---|---|---|
| LOFT Experiment LP-02-6 Analysis by RELAP5/MOD2 Code with Improved Minimum Film Boiling Temperature | Journal of Nuclear Science and Technology |
| 1 | 1988 |
| A study on surface rewet caused by uniform collapse of flow film boiling. | Transactions of the Japan Society of Mechanical Engineers Series B | 1 | 1987 | |
| Measurements of true quench temperature of subcooled water under forced convective conditions | International Journal of Heat and Mass Transfer |
| 20 | 1985 |
| Heat Transfer Calculation of Simulated Heater Rods throughout Reflood Phase in Postulated PWR-LOCA Experiments | Journal of Nuclear Science and Technology |
| 8 | 1983 |
| Measurement of boiling curves during rewetting of a hot circular duct | International Journal of Heat and Mass Transfer |
| 27 | 1979 |
Citations
| Title | Journal | Journal Categories | Citations | Publication Date |
|---|---|---|---|---|
| Analysis of main steam line break accident on a BWR test facility using TRACE | Nuclear Engineering and Design |
| 1 | 2024 |
| Analysis of LBLOCA of APR1400 with 3D RPV model using TRACE | Nuclear Engineering and Technology |
| 2023 | |
| Full scope simulation of VVER-1000 blowdown source and containment pressurization in a LBLOCA by parallel coupling of TRACE and CONTAIN | Progress in Nuclear Energy |
| 3 | 2021 |
Evaluation of Passive Safety Injection System Performance Under Large Break LOCA for Qinshan PWR | Frontiers in Energy Research |
| 2021 |
Citations Analysis
The category
Technology: Engineering (General). Civil engineering (General) 4
is the most commonly referenced area in studies that cite this article. The first research to cite this article was titled Full scope simulation of VVER-1000 blowdown source and containment pressurization in a LBLOCA by parallel coupling of TRACE and CONTAIN and was published in 2021. The most recent citation comes from a 2024 study titled Analysis of main steam line break accident on a BWR test facility using TRACE. This article reached its peak citation in 2021, with 2 citations. It has been cited in 4 different journals, 50% of which are open access. Among related journals, the Nuclear Engineering and Design cited this research the most, with 1 citations. The chart below illustrates the annual citation trends for this article.