Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2015, Article ID 913274, 7 pages
http://dx.doi.org/10.1155/2015/913274
Research Article

Full Scope Modeling and Analysis on the Secondary Circuit of Chinese Large-Capacity Advanced PWR Based on RELAP5 Code

1School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
2Beijing Key Laboratory of Passive Nuclear Safety Technology, North China Electric Power University, Beijing 102206, China
3State Nuclear Electric Power Planning Design & Research Institute, Beijing 100095, China

Received 2 March 2015; Revised 3 June 2015; Accepted 4 June 2015

Academic Editor: Iztok Tiselj

Copyright © 2015 Dao-gang Lu et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. L. L. Briggs, “A new balance-of-plant model for the SASSYS-1 LMR systems analysis code,” Transactions of the American Nuclear Society, vol. 60, p. 709, 1989. View at Google Scholar
  2. H. P. Planchon, R. M. Singer, D. Mohr, E. E. Feldman, L. K. Chang, and P. R. Betten, “The experimental breeder reactor II inherent shutdown and heat removal tests—results and analysis,” Nuclear Engineering and Design, vol. 91, no. 3, pp. 287–296, 1986. View at Publisher · View at Google Scholar · View at Scopus
  3. H. A. Larson, E. M. Dean, J. F. Koenig, J. G. Gale, and W. K. Lehto, “Dynamic simulator for nuclear power plants (DSNP): development, verification and expansion of modules,” in Proceedings of the International Conference on Power Plant Simulation, CONF-851007-15, Cuernavaca, Mexico, November 1984.
  4. P. Sharma, K. Natesan, P. Selvaraj, V. Balasubramaniyan, and P. Chellapandi, “Dynamic modeling of steam water system of prototype fast breeder reactor using RELAP code,” Annals of Nuclear Energy, vol. 68, pp. 209–219, 2014. View at Publisher · View at Google Scholar · View at Scopus
  5. C.-Y. Yang, T. K. S. Liang, B. S. Pei, C. K. Shih, S. C. Chiang, and L. C. Wang, “Development and application of a dual RELAP5-3D-based engineering simulator for ABWR,” Nuclear Engineering and Design, vol. 239, no. 10, pp. 1847–1856, 2009. View at Publisher · View at Google Scholar · View at Scopus
  6. Q. Zhang, R. Guo, C. Zhang, X. Chen, and B. Wang, “Radioactive airborne effluents and the environmental impact assessment of CAP1400 nuclear power plant under normal operation,” Nuclear Engineering and Design, vol. 280, pp. 579–585, 2014. View at Publisher · View at Google Scholar
  7. Nuclear Safety Analysis Division, RELAPS/MOD3.3 Code Manual Volume I: Code Structure, System models, and Solution Methods, Information Systems Laboratories, 2001.
  8. M. Dulau and D. Bica, “Mathematical modelling and simulation of the behaviour of the steam turbine,” Procedia Technology, vol. 12, pp. 723–729, 2014. View at Publisher · View at Google Scholar
  9. T. C. Elliott, K. Chen, and R. Swanekamp, Standard Handbook of Powerplant Engineering, McGraw-Hill, New York, NY, USA, 2nd edition, 1997.
  10. M. Álvarez-Fernández, L. D. Portillo-Valdés, and C. Alonso-Tristán, “Thermal analysis of closed feedwater heaters in nuclear power plants,” Applied Thermal Engineering, vol. 68, no. 1-2, pp. 45–58, 2014. View at Publisher · View at Google Scholar · View at Scopus
  11. S. C. Stultz, Steam: Its Generation and Use, Babcock & Wilcox, 41st edition, 2005.