Thermal-hydraulic Assessment of Seven Wire-wrapped rod Bundle

Kefeng Lyu; Xuelei Sheng; Xudan Ma

doi:10.1051/e3sconf/202021201009

All issues

Volume 212 (2020)

E3S Web Conf., 212 (2020) 01009

References

Open Access

Issue		E3S Web Conf. Volume 212, 2020 2020 International Conference on Building Energy Conservation, Thermal Safety and Environmental Pollution Control (ICBTE 2020)


Article Number		01009
Number of page(s)		9
Section		Ecology and Energy Saving
DOI		https://doi.org/10.1051/e3sconf/202021201009
Published online		26 November 2020

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[1] C. Rubbia, 1996. Status of the Energy Amplifier Concept. Proceeding of the 2 nd International Conference on Accerator-driven Transmutation Technologies and Applications, Kalmar, Sweden, June 3-7. [Google Scholar]

[2] E.H. Novendstern, 1972. Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrap spacer system[J]. Nucl. Eng. Des. 22: 19-27 [CrossRef] [Google Scholar]

[3] J. Pacio, M. Daubner, F. Fellmoser, et al, 2014. Heavy-liquid metal heat transfer experiment in a 19-rod bundle with grid spacers. Nucl. Eng. Des. 273, 33–46. [CrossRef] [Google Scholar]

[4] K. Rehme, 1972. Pressure drop performance of rod bundles in hexagonal arrangements. Int. J. Heat Mass Transfer 15 (12), 2499–2517. [CrossRef] [Google Scholar]

[5] K. Mikityuk, 2009. Heat transfer to liquid metal: review of data and correlations for tube bundles. Nucl. Eng. Des. 239 (4), 680–687. [CrossRef] [Google Scholar]

[6] L. Qiu, Y. Wu. B. Xiao, et al, 2000. A low Aspect Ratio Tokamak Transmutation System. Nucl Fusion. 40: 629-633. [CrossRef] [Google Scholar]

[7] M. Berthoux, T. Cadiou, 2010. The Thermal Hydraulics in a Rod Bundle Representative if the Start-up Core of the ALLEGRO Gas Cooled Fast Reactor-Experimental and Numerical Approaches. Nucl. Eng. Des. 240, 3372–3386. [CrossRef] [Google Scholar]

[8] M. Tarantino, I. Di Piazza, P. Agostini, et al, 2013. Thermal-hydraulic Assessment of HLM-cooled Pin Bundle in CIRCE Pool Facility. International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios FR13. Paris, France, March 4-7, 2013. [Google Scholar]

[9] N. Li, 2008. Lead-alloy Coolant Technology and Materials-technology Readiness Level Evaluation. Progress in Nuclear Energy. 50, 140-151. [CrossRef] [Google Scholar]

[10] N. Govindha Rasu, K. Velusamy, T. Sundararajan, et al, 2013. Investigations of flow and temperature field development in bare and wire-wrapped reactor fuel pin bundles cooled by sodium. [Google Scholar]

[11] OECD/NEA, 2007. Handbook on Lead-Bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal–Hydraulics and Technologies. 2007 edition: 15-21. [Google Scholar]

[12] Q. Huang, S. Gao, Z. Zhu, et al. 2009. Progress in Compatibility Experiments on Lithium-Lead with Candidate Structural Materials for Fusion in China. [J]. Fusion Eng. Des. 84: 242-246. [CrossRef] [Google Scholar]

[13] Q. Huang, C. Li, Y. Li, et al, 2007. Progress in Development of China Low Activation Martensitic Steel for Fusion Applicayion. J. Nucl. Mater. 367-370: 142-146. [CrossRef] [Google Scholar]

[14] T. Takizuka, K. Tsujimoto, T. Sasa, et al, 2002. Design Study of Lead-bismuth Cooled ADS Dedicated to Nuclear Waste Transmutation. Progress in Nuclear Energy. 40, 505-512. [CrossRef] [Google Scholar]

[15] W. Gudowski, V. Arzhanov, C. Broeders, et al, 2001. Review of the European project — Impact of Accelerator-Based Technologies on nuclear fission safety (IABAT). Progress in Nuclear Energy. 38, 135-151. [CrossRef] [Google Scholar]

[16] W. Pfrang, D. Struwe, 2007. Assessment of correlations for heat transfer to the coolant for heavy liquid metal cooled core designs. Technical Report FZKA 7352, Forschunszentrum Karlsruhe GmbH. [Google Scholar]

[17] X. Cheng, N. Tak, 2006. Investigation on Turbulent Heat Transfer to Lead-bismuth Eutectic Flows in Circular Tubes for Nuclear Applications. Nucl. Eng. Des. 236, 385-393. [CrossRef] [Google Scholar]