CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review

Md. Wazihur Rahman; Md. Saadbin Chowdhury; Mohammad Zoynal Abedin

doi:doi:10.11648/j.ajset.20240902.11

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CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review

Md. Wazihur Rahman

, Md. Saadbin Chowdhury

, Mohammad Zoynal Abedin

Published in American Journal of Science, Engineering and Technology (Volume 9, Issue 2)

Received: 12 March 2024 Accepted: 25 March 2024 Published: 11 April 2024

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Abstract

This comprehensive review explores the application of Computational Fluid Dynamics (CFD) in analyzing coolant flow within Reactor Pressure Vessels (RPVs) of nuclear power plants. By synthesizing existing research, methodologies, and advancements specific to RPVs, the paper offers in-depth insights into critical aspects such as boundary conditions, turbulence modeling, heat transfer mechanisms, and validation techniques. Examining a range of studies encompassing various reactor types from Pressurized Water Reactors (PWRs) to Integral Pressurized Water Reactors (IPWRs), the review underscores CFD's pivotal role in enhancing safety, efficiency, and performance optimization in nuclear reactors. Through systematic exploration, this study underscores the critical importance of precise modeling in facilitating safety assessments, operational optimization, and design enhancements across various reactor systems. Accurate modeling serves as a cornerstone for informed decision-making processes aimed at maximizing reactor performance while ensuring the highest standards of safety and reliability. The paper navigates through challenges such as computational limitations and turbulence modeling intricacies, while also discussing emerging trends like the porous media method aimed at improving computational efficiency. By offering a comprehensive understanding of thermal-hydraulic behavior in nuclear reactors, the review underscores CFD's contribution to enhancing safety and reliability in nuclear power generation. Overall, this review underscores the indispensable role of CFD in advancing our understanding of nuclear reactor dynamics, thereby contributing significantly to the overarching goals of improved safety and reliability in nuclear power generation.

Published in	American Journal of Science, Engineering and Technology (Volume 9, Issue 2)
DOI	10.11648/j.ajset.20240902.11
Page(s)	42-49
Creative Commons	This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.
Copyright	Copyright © The Author(s), 2024. Published by Science Publishing Group

Keywords

Computational Fluid Dynamics, Reactor Pressure Vessel, Coolant Flow, Thermal-Hydraulic Behavior, Safety, Nuclear Power Plant

References

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[3]	Electrical Easy. Basic Layout and Working of a Nuclear Power Plant. Available from: https://www.electricaleasy.com/2015/09/nuclear-power-plant.html [Accessed 2021].
[4]	Pavel Polach and Michal Hajžman, ECCOMAS Congress 2016, VII European Congress on Computational Methods in Applied Sciences and Engineering, M. Papadrakakis, V. Papadopoulos, G. Stefanou, V. Plevris (eds.), Crete Island, Greece, 5–10 June 2016.
[5]	Nuclear Power. Reactor Pressure Vessel. Available from: https://www.nuclear-power.com/nuclear-power-plant/nuclear-reactor/reactor-pressure-vessel/ [Accessed 2024].
[6]	Wikipedia. Nuclear Reactor Coolant. Available from: https://en.wikipedia.org/wiki/Nuclear_reactor_coolant [Accessed 19 January 2024].
[7]	Wikipedia. Computational Fluid Dynamics. Available from: https://en.wikipedia.org/wiki/Computational_fluid_dynamics [Accessed 20 January 2024].
[8]	Simscale. What is CFD \| Computational Fluid Dynamics? Available from: https://www.simscale.com/docs/simwiki/cfd-computational-fluid-dynamics/what-is-cfd-computational-fluid-dynamics/ [Accessed 7 December 2023].
[9]	H. Farajollahi, A. Ghasemizad, and B. Khanbabaei, "Journal of Sciences, 2008, 19(3), 273-281.
[10]	Lin Sun, Minjun Peng, Genglei Xia, Xing Lv, and Ren Li, Nuclear Engineering and Technology. 2017, 49, 71-81.
[11]	B. Khanbabaei, A. Ghasemizad, H. Farajollahi, CFD-calculation of fluid flow in VVER-1000 reactors, J. Appl. Sci. 2008, 8(5), 780–787.
[12]	Shojja Ayed Aljasar, Oleg. Yu Dolmatov, Muhammad Saqib & Yubin Xu, International Journal of Mechanical and Production Engineering Research and Development (IJMPERD), 2020, Vol. 10, Issue 2, 1419–1428.
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[14]	Huseyin Ayhan, Sule Ergun, Ayhan and Erg¨un/ BgNS conference 18-21 September 2013.
[15]	B. Kütük and I. H. Güzelbey, International Journal of Pressure Vessels and Piping. 2020, 187(2020) 104165.
[16]	Taosif Alam and M. A. R. Sarkar, International Conference on Mechanical, Industrial and Energy Engineering 2018, 23-24 December, 2018, Khulna, Bangladesh.

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APA Style

Rahman, M. W., Chowdhury, M. S., Abedin, M. Z. (2024). CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review. American Journal of Science, Engineering and Technology, 9(2), 42-49. https://doi.org/10.11648/j.ajset.20240902.11

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ACS Style

Rahman, M. W.; Chowdhury, M. S.; Abedin, M. Z. CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review. Am. J. Sci. Eng. Technol. 2024, 9(2), 42-49. doi: 10.11648/j.ajset.20240902.11

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AMA Style

Rahman MW, Chowdhury MS, Abedin MZ. CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review. Am J Sci Eng Technol. 2024;9(2):42-49. doi: 10.11648/j.ajset.20240902.11

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@article{10.11648/j.ajset.20240902.11,
  author = {Md. Wazihur Rahman and Md. Saadbin Chowdhury and Mohammad Zoynal Abedin},
  title = {CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review
},
  journal = {American Journal of Science, Engineering and Technology},
  volume = {9},
  number = {2},
  pages = {42-49},
  doi = {10.11648/j.ajset.20240902.11},
  url = {https://doi.org/10.11648/j.ajset.20240902.11},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ajset.20240902.11},
  abstract = {This comprehensive review explores the application of Computational Fluid Dynamics (CFD) in analyzing coolant flow within Reactor Pressure Vessels (RPVs) of nuclear power plants. By synthesizing existing research, methodologies, and advancements specific to RPVs, the paper offers in-depth insights into critical aspects such as boundary conditions, turbulence modeling, heat transfer mechanisms, and validation techniques. Examining a range of studies encompassing various reactor types from Pressurized Water Reactors (PWRs) to Integral Pressurized Water Reactors (IPWRs), the review underscores CFD's pivotal role in enhancing safety, efficiency, and performance optimization in nuclear reactors. Through systematic exploration, this study underscores the critical importance of precise modeling in facilitating safety assessments, operational optimization, and design enhancements across various reactor systems. Accurate modeling serves as a cornerstone for informed decision-making processes aimed at maximizing reactor performance while ensuring the highest standards of safety and reliability. The paper navigates through challenges such as computational limitations and turbulence modeling intricacies, while also discussing emerging trends like the porous media method aimed at improving computational efficiency. By offering a comprehensive understanding of thermal-hydraulic behavior in nuclear reactors, the review underscores CFD's contribution to enhancing safety and reliability in nuclear power generation. Overall, this review underscores the indispensable role of CFD in advancing our understanding of nuclear reactor dynamics, thereby contributing significantly to the overarching goals of improved safety and reliability in nuclear power generation.
},
 year = {2024}
}

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TY  - JOUR
T1  - CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review

AU  - Md. Wazihur Rahman
AU  - Md. Saadbin Chowdhury
AU  - Mohammad Zoynal Abedin
Y1  - 2024/04/11
PY  - 2024
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DO  - 10.11648/j.ajset.20240902.11
T2  - American Journal of Science, Engineering and Technology
JF  - American Journal of Science, Engineering and Technology
JO  - American Journal of Science, Engineering and Technology
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EP  - 49
PB  - Science Publishing Group
SN  - 2578-8353
UR  - https://doi.org/10.11648/j.ajset.20240902.11
AB  - This comprehensive review explores the application of Computational Fluid Dynamics (CFD) in analyzing coolant flow within Reactor Pressure Vessels (RPVs) of nuclear power plants. By synthesizing existing research, methodologies, and advancements specific to RPVs, the paper offers in-depth insights into critical aspects such as boundary conditions, turbulence modeling, heat transfer mechanisms, and validation techniques. Examining a range of studies encompassing various reactor types from Pressurized Water Reactors (PWRs) to Integral Pressurized Water Reactors (IPWRs), the review underscores CFD's pivotal role in enhancing safety, efficiency, and performance optimization in nuclear reactors. Through systematic exploration, this study underscores the critical importance of precise modeling in facilitating safety assessments, operational optimization, and design enhancements across various reactor systems. Accurate modeling serves as a cornerstone for informed decision-making processes aimed at maximizing reactor performance while ensuring the highest standards of safety and reliability. The paper navigates through challenges such as computational limitations and turbulence modeling intricacies, while also discussing emerging trends like the porous media method aimed at improving computational efficiency. By offering a comprehensive understanding of thermal-hydraulic behavior in nuclear reactors, the review underscores CFD's contribution to enhancing safety and reliability in nuclear power generation. Overall, this review underscores the indispensable role of CFD in advancing our understanding of nuclear reactor dynamics, thereby contributing significantly to the overarching goals of improved safety and reliability in nuclear power generation.

VL  - 9
IS  - 2
ER  -

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Author Information

Md. Wazihur Rahman

Department of Mechanical Engineering, Dhaka University of Engineering and Technology, Gazipur, Bangladesh

Contact Email

http://orcid.org/0009-0003-7406-2415
Md. Saadbin Chowdhury

Department of Mechanical Engineering, Dhaka University of Engineering and Technology, Gazipur, Bangladesh；Department of Mechanical Engineering, Bangladesh University of Engineering and Technology, Dhaka, Bangladesh

Contact Email

http://orcid.org/0009-0009-7774-4378
Mohammad Zoynal Abedin

Department of Mechanical Engineering, Dhaka University of Engineering and Technology, Gazipur, Bangladesh

Contact Email

http://orcid.org/0000-0002-3268-1387

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APA Style

Rahman, M. W., Chowdhury, M. S., Abedin, M. Z. (2024). CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review. American Journal of Science, Engineering and Technology, 9(2), 42-49. https://doi.org/10.11648/j.ajset.20240902.11

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ACS Style

Rahman, M. W.; Chowdhury, M. S.; Abedin, M. Z. CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review. Am. J. Sci. Eng. Technol. 2024, 9(2), 42-49. doi: 10.11648/j.ajset.20240902.11

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AMA Style

Rahman MW, Chowdhury MS, Abedin MZ. CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review. Am J Sci Eng Technol. 2024;9(2):42-49. doi: 10.11648/j.ajset.20240902.11

Copy | Download

@article{10.11648/j.ajset.20240902.11,
  author = {Md. Wazihur Rahman and Md. Saadbin Chowdhury and Mohammad Zoynal Abedin},
  title = {CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review
},
  journal = {American Journal of Science, Engineering and Technology},
  volume = {9},
  number = {2},
  pages = {42-49},
  doi = {10.11648/j.ajset.20240902.11},
  url = {https://doi.org/10.11648/j.ajset.20240902.11},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ajset.20240902.11},
  abstract = {This comprehensive review explores the application of Computational Fluid Dynamics (CFD) in analyzing coolant flow within Reactor Pressure Vessels (RPVs) of nuclear power plants. By synthesizing existing research, methodologies, and advancements specific to RPVs, the paper offers in-depth insights into critical aspects such as boundary conditions, turbulence modeling, heat transfer mechanisms, and validation techniques. Examining a range of studies encompassing various reactor types from Pressurized Water Reactors (PWRs) to Integral Pressurized Water Reactors (IPWRs), the review underscores CFD's pivotal role in enhancing safety, efficiency, and performance optimization in nuclear reactors. Through systematic exploration, this study underscores the critical importance of precise modeling in facilitating safety assessments, operational optimization, and design enhancements across various reactor systems. Accurate modeling serves as a cornerstone for informed decision-making processes aimed at maximizing reactor performance while ensuring the highest standards of safety and reliability. The paper navigates through challenges such as computational limitations and turbulence modeling intricacies, while also discussing emerging trends like the porous media method aimed at improving computational efficiency. By offering a comprehensive understanding of thermal-hydraulic behavior in nuclear reactors, the review underscores CFD's contribution to enhancing safety and reliability in nuclear power generation. Overall, this review underscores the indispensable role of CFD in advancing our understanding of nuclear reactor dynamics, thereby contributing significantly to the overarching goals of improved safety and reliability in nuclear power generation.
},
 year = {2024}
}

Copy | Download

TY  - JOUR
T1  - CFD Analysis of Coolant Flow Characteristics in Reactor Pressure Vessel: A Comprehensive Review

AU  - Md. Wazihur Rahman
AU  - Md. Saadbin Chowdhury
AU  - Mohammad Zoynal Abedin
Y1  - 2024/04/11
PY  - 2024
N1  - https://doi.org/10.11648/j.ajset.20240902.11
DO  - 10.11648/j.ajset.20240902.11
T2  - American Journal of Science, Engineering and Technology
JF  - American Journal of Science, Engineering and Technology
JO  - American Journal of Science, Engineering and Technology
SP  - 42
EP  - 49
PB  - Science Publishing Group
SN  - 2578-8353
UR  - https://doi.org/10.11648/j.ajset.20240902.11
AB  - This comprehensive review explores the application of Computational Fluid Dynamics (CFD) in analyzing coolant flow within Reactor Pressure Vessels (RPVs) of nuclear power plants. By synthesizing existing research, methodologies, and advancements specific to RPVs, the paper offers in-depth insights into critical aspects such as boundary conditions, turbulence modeling, heat transfer mechanisms, and validation techniques. Examining a range of studies encompassing various reactor types from Pressurized Water Reactors (PWRs) to Integral Pressurized Water Reactors (IPWRs), the review underscores CFD's pivotal role in enhancing safety, efficiency, and performance optimization in nuclear reactors. Through systematic exploration, this study underscores the critical importance of precise modeling in facilitating safety assessments, operational optimization, and design enhancements across various reactor systems. Accurate modeling serves as a cornerstone for informed decision-making processes aimed at maximizing reactor performance while ensuring the highest standards of safety and reliability. The paper navigates through challenges such as computational limitations and turbulence modeling intricacies, while also discussing emerging trends like the porous media method aimed at improving computational efficiency. By offering a comprehensive understanding of thermal-hydraulic behavior in nuclear reactors, the review underscores CFD's contribution to enhancing safety and reliability in nuclear power generation. Overall, this review underscores the indispensable role of CFD in advancing our understanding of nuclear reactor dynamics, thereby contributing significantly to the overarching goals of improved safety and reliability in nuclear power generation.

VL  - 9
IS  - 2
ER  -

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