Open Access
Issue
E3S Web Conf.
Volume 136, 2019
2019 International Conference on Building Energy Conservation, Thermal Safety and Environmental Pollution Control (ICBTE 2019)
Article Number 01044
Number of page(s) 4
Section Ultra-Low Energy Consumption Building Technology
DOI https://doi.org/10.1051/e3sconf/201913601044
Published online 10 December 2019
  1. C. Rubbia, Status of the Energy Amplifier Concept. Proceeding of the 2nd International Conference on Accerator-driven Transmutation Technologies and Applications, Kalmar, Sweden, June 3-7. (1996) [Google Scholar]
  2. E.H. Novendstern, Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrap spacer system[J]. Nucl. Eng. Des. 22: 19-27 (1972) [CrossRef] [Google Scholar]
  3. J. Pacio, M. Daubner, F. Fellmoser, et al, Heavy-liquid metal heat transfer experiment in a 19-rod bundle with grid spacers. Nucl. Eng. Des. 273, 33–46. (2014) [CrossRef] [Google Scholar]
  4. K. Rehme, Pressure drop performance of rod bundles in hexagonal arrangements. Int. J. Heat Mass Transfer 15 (12), 2499–2517. (1972) [CrossRef] [Google Scholar]
  5. K. Mikityuk, Heat transfer to liquid metal: review of data and correlations for tube bundles. Nucl. Eng. Des. 239 (4), 680–687. (2009) [CrossRef] [Google Scholar]
  6. L. Qiu, Y. Wu. B. Xiao, et al, A low Aspect Ratio Tokamak Transmutation System. Nucl Fusion. 40: 629-633. (2000) [CrossRef] [Google Scholar]
  7. M. Berthoux, T. Cadiou, 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. (2010) [CrossRef] [Google Scholar]
  8. M. Tarantino, I. Di Piazza, P. Agostini, et al, 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. (2013) [Google Scholar]
  9. N. Li, Lead-alloy Coolant Technology and Materials-technology Readiness Level Evaluation. Progress in Nuclear Energy. 50, 140-151. (2008) [CrossRef] [Google Scholar]
  10. N. Govindha Rasu, K. Velusamy, T. Sundararajan, et al, Investigations of flow and temperature field development in bare and wire-wrapped reactor fuel pin bundles cooled by sodium. (2013) [Google Scholar]
  11. OECD/NEA, Handbook on Lead-Bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal–Hydraulics and Technologies. 2007 edition: 15-21. (2007) [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.