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 | |
- 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]
- 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]
- 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]
- K. Rehme, 1972. Pressure drop performance of rod bundles in hexagonal arrangements. Int. J. Heat Mass Transfer 15 (12), 2499–2517. [CrossRef] [Google Scholar]
- 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]
- L. Qiu, Y. Wu. B. Xiao, et al, 2000. A low Aspect Ratio Tokamak Transmutation System. Nucl Fusion. 40: 629-633. [CrossRef] [Google Scholar]
- 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]
- 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]
- N. Li, 2008. Lead-alloy Coolant Technology and Materials-technology Readiness Level Evaluation. Progress in Nuclear Energy. 50, 140-151. [CrossRef] [Google Scholar]
- 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]
- OECD/NEA, 2007. Handbook on Lead-Bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal–Hydraulics and Technologies. 2007 edition: 15-21. [Google Scholar]
- 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]
- 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]
- 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]
- 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]
- 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]
- 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]
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