Comparison of thermal hydraulic performance between horizontal and vertical steam generators in nuclear power plants
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Neama M. El-Sahlamy
Abstract
Steam generators (SG) for Nuclear Power Plants (NPPs) are important large-sized metal consuming equipment of nuclear power installations. Efficiency of steam generator operation determines the overall service life of the whole nuclear facility. Vertical steam generators are used normally in North America, Europe and South East Asia, but horizontal steam generators are currently of great importance to reduce building heights and construction costs that govern the overall cost of new nuclear power plants. The objective of the current study is to measure the performance of nuclear steam generators in NPPs through comparative assessments of vertical and horizontal configurations. For this purpose, the vertical U-tube steam generators of a typical 4-loop Pressurized Water Reactor (PWR) was replaced by a VVER-1000 horizontal steam generators to evaluate the horizontal SG performance, at the same plant conditions and characteristics, in comparison with the vertical SG. The thermal hydraulic system code RELAP5 was used in the current work to perform the required analysis, during steady and transient scenarios.
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Research ethics: Not applicable.
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Author contributions: The author has accepted responsibility for the entire content of this manuscript and approved its submission.
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Competing interests: The author states no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
References
Auvinen, A., Jokiniemi, J.K., Lӓhde, A., Routamo, T., Lundstrӧm, P., Tuomisto, H., Dienstbier, J., Güntay, S., Suckow, D., Dehbi, A., et al.. (2005). Steam generator tube rupture (SGTR) scenarios. Nucl. Eng. Des. 235: 457–472, https://doi.org/10.1016/j.nucengdes.2004.08.060.Search in Google Scholar
Egorov, M.Y. (2019). Vertical steam generators for VVER NPPs. Nucl. Energy Technol. 5: 31–38, https://doi.org/10.3897/nucet.5.33980.Search in Google Scholar
El-Sahlamy, N., Hassan, M., and Khedr, A. (2020). Comparison between standard solid fuel and a new annular fuel performance in the core of a PWR. Kerntechnik 85: 161–168, https://doi.org/10.3139/124.190020.Search in Google Scholar
El-Sahlamy, N.M. and Elsaid, A.M. (2021). Effect of ECCS cold-leg injection angle on thermal hydraulic characteristics and core recovery during LBLOCA in a PWR. Prog. Nucl. Energy 142: 1–14, https://doi.org/10.1016/j.pnucene.2021.104033.Search in Google Scholar
Helmy, S., Khedr, A., and D’Auria, F. (2018). Analysis of break size effects on SBLOCA scenario in a 4-loop PWR using RELAP5/MOD3.3. Int. J. Eng. Sci. 7: 36–43.Search in Google Scholar
Hovi, V., Pättikangas, T., and Riikonen, V. (2016). Coupled one-dimensional and CFD models for the simulation of steam generators. Nucl. Eng. Des. 310: 93–111, https://doi.org/10.1016/j.nucengdes.2016.09.023.Search in Google Scholar
Khedr, A., El-Sahlamy, N., Helmy, S., and D’Auria, F. (2017). Comparative study between cold-leg and hot-leg safety injection during SBLOCA in a 4 loop PWR NPP. Int. J. Eng. Sci. 6: 31–37.Search in Google Scholar
RELAP5/MOD3 Code Manual. (1995). Volume I: code structure, system models and solution methods. NUREG/CR-5535-V1.Search in Google Scholar
Trunov, N., Denisov, V., Kharchenko, S., and Lukasevich, B. (2006). Сonsideration of field experience in developing new projects of steam generators for nuclear power stations equipped with VVER reactors. Therm. Eng. 53: 37–42, https://doi.org/10.1134/S004060150601006X.Search in Google Scholar
Trunov, N., Ryzhov, S., and Davidenko, S. (2011). Horizontal steam generators: problems and prospects. Therm. Eng. 58: 179–183, https://doi.org/10.1134/S004060151103013X.Search in Google Scholar
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Articles in the same Issue
- Frontmatter
- Evaluation of the optimum safety performance of the nuclear reactor compact grounding system under lightning strikes and ground fault
- An artificial neural network-based numerical estimation of the boiling pressure drop of different refrigerants flowing in smooth and micro-fin tubes
- Application of internal fire probabilistic risk assessment in design optimization for marine SMR
- Generic flame extension model development based on machine learning for NPPs fire hazard analysis (FHA)
- Comparison of thermal hydraulic performance between horizontal and vertical steam generators in nuclear power plants
- The RADTRAD analysis methodology for the Fuel Handling Accident during the long-term shutdown period of Chinshan Nuclear Power Plant
- A blockchain based scheme for distributed storage of nuclear power plant images
- Scaling factors for CANDU reactor waste: how reliable are they?
- Calendar of events
