Numerical Analysis of Straight Wire and Helical Wire wrap 2×2 Rod Bundle with Supercritical Water

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Year : 2025 | Volume : 15 | Issue : 03 | Page :
    By

    Gaurav Kumar,

  • Raj Kumar Singh,

  1. Research Scholar, Department of Mechanical Engineering, Delhi Technological University, Delhi, India
  2. Professor, Department of Mechanical Engineering, Delhi Technological University, Delhi, India

Abstract

Investigations using computational fluid dynamics (CFD) have been conducted on a 2×2 rod bundle that has been wrapped with both straight and helical spacer wires. The bundle has been wrapped with both types of spacer wires. There have been investigations conducted in this regard. The wires that have been coiled have been wrapped around another rod bundle that has been looped around them. An examination and investigation into the employment of helical wire spacer has been carried out in the past. This assessment and investigation has been carried out. In order to construct flow disseminations in the rod bundle, it is possible to use a commercial computer to solve the equations for the conservation of mass, momentum, and energy that are contained within the Ansys fluent software. This will allow the flow disseminations to be constructed. The generation of flow disseminations will be made possible as a result of this. During its passage through the rod bundle, it is possible to observe that the supercritical water flows not only in the axial direction but also in the transverse direction. This is something that can be accomplished. At this point, it is possible to make this observation. Specifically, this is because the spacer is wrapped in a helical form, which permits the water to flow in both directions. This is the reason why this occurs. As a result of the presence of this transverse flow, the coolant is dispersed among the sub-channels in a manner that is even more comprehensive than it would have been under any other set of circumstances.

Keywords: CFD; Rod; Supercritical Water; Wire; Hydraulics

[This article belongs to Journal of Nuclear Engineering & Technology ]

How to cite this article:
Gaurav Kumar, Raj Kumar Singh. Numerical Analysis of Straight Wire and Helical Wire wrap 2×2 Rod Bundle with Supercritical Water. Journal of Nuclear Engineering & Technology. 2025; 15(03):-.
How to cite this URL:
Gaurav Kumar, Raj Kumar Singh. Numerical Analysis of Straight Wire and Helical Wire wrap 2×2 Rod Bundle with Supercritical Water. Journal of Nuclear Engineering & Technology. 2025; 15(03):-. Available from: https://journals.stmjournals.com/jonet/article=2025/view=232819


References

  1.  Zang J, Yan X, Li Y, Zeng X, Huang Y. The flow resistance experiments of supercritical pressure water in 2 × 2 rod bundle. Int J Heat Mass Transf. 2020 Feb 1;147:118991.
  2. Zhao M, Wang F, Badea AF. Evaluation and development of heat transfer model for supercritical water flowing in 2 × 2 rod bundles with spacer grid. Int J Heat Mass Transf. 2021 Feb 1;165:120651.
  3. Lin J, Huang M, Zhang S, Wang B, Huang J, Matsuda H, et al. CFD investigation for a 7-pin wrapped-wire fuel assembly with different wires. Ann Nucl Energy. 2021 Dec 15;164:108582.
  4. Lyu K, Sheng X, Ma X, Wang H, Shi W, Cheng Z. Numerical investigation of thermal hydraulic behaviors in wire-wrapped bundle with smaller wire diameter of peripheral rods. Ann Nucl Energy. 2021 Dec 1;163:108526.
  5. Liang Y, Zhang D, Chen Y, Zhang K, Tian W, Qiu S, et al. An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle. Appl Therm Eng. 2020 Jun 25;174:115311.
  6. Todreas N, Chen SK, Pacio J. Adventures in study of the pressure losses in wire- wrapped rod bundle arrays. Nucl Eng Des. 2020 Dec 15;370:110934.
  7. Qiu H, Li J, Dong Z, Wang M, Tian W, Su GH. Numerical study on inter-wrapper flow and heat transfer characteristics in liquid metal-cooled fast reactors. Prog Nucl Energy. 2023 Jan 1;155:104534.
  8. Liu S, Zhu D, Li X, Tian R. CFD investigation of flow and heat transfer of supercritical CO₂ in wire wrapped rod bundle. Nucl Eng Des. 2023 Aug 15;410:112405.
  9. Li J, Xiao Y, Cong T, Xiong Z, Gu H. Numerical analysis of the subcooled boiling phenomena in a wire-wrapped annulus. Int J Heat Mass Transf. 2023 Feb 1;201:123519.
  10. Li Y, Wei T, Feng S, Sun R, Tian R, Tan S. Numerical study on flow and heat transfer of lead–bismuth eutectic in wire-wrapped fuel assembly under typical ocean condition. Nucl Eng Des. 2024 May 1;421:112740.
  11. Hata K, Fukuda K, Mizuuchi T. Laminar natural convection heat transfer from vertical 7×7 rod bundles in liquid sodium. J Nucl Eng Radiat Sci. 2019 Apr 1;5(2):021002.
  12. Xiao Y, Pan J, Gu H. Numerical investigation of spacer effects on heat transfer of supercritical fluid flow in an annular channel. Int J Heat Mass Transf. 2018 Jun 1;121:343–53.
  13. Wang H, Bi Q, Leung LKH. Heat transfer from a 2 × 2 wire-wrapped rod bundle to supercritical pressure water. Int J Heat Mass Transf. 2016 Jun 1;97:486–501.
  14. Shan J, Wang H, Liu W, Song L, Chen X, Jiang Y. Subchannel analysis of wire wrapped SCWR assembly. Sci Technol Nucl Install. 2014 Feb 23;2014:1–8.
  15. Podila K, Rao Y. Computational fluid dynamic simulations of heat transfer from a 2 × 2 wire-wrapped fuel rod bundle to supercritical pressure water. J Nucl Eng Radiat Sci. 2017 Aug 25;4(1):011008.
Regular Issue Subscription Original Research
Volume 15
Issue 03
Received 01/02/2025
Accepted 07/07/2025
Published 22/11/2025
Publication Time 294 Days
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