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Science and Technology of Nuclear Installations
Volume 2015, Article ID 302648, 13 pages
http://dx.doi.org/10.1155/2015/302648
Research Article

Temperature Response of the HTR-10 during the Power Ascension Test

Institute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, China

Received 5 June 2015; Revised 25 August 2015; Accepted 26 August 2015

Academic Editor: Alejandro Clausse

Copyright © 2015 Fubing Chen 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. S. Hu and R. Wang, “Power operation commissioning tests of HTR-10,” in Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology (HTR '04), Beijing, China, September 2004.
  2. Z. Wu, D. Lin, and D. Zhong, “The design features of the HTR-10,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 25–32, 2002. View at Publisher · View at Google Scholar · View at Scopus
  3. R. Li and H. Ju, “Structural design and two-phase flow stability test for the steam generator,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 179–187, 2002. View at Publisher · View at Google Scholar · View at Scopus
  4. S. Hu, X. Liang, and L. Wei, “Commissioning and operation experience and safety experiments on HTR-10,” in Proceedings of the 3rd International Topical Meeting on High Temperature Reactor Technology (HTR '06), Johannesburg, South Africa, October 2006.
  5. Q. Su, R. Wang, S. Hu, X. Liang, H. Chen, and L. Liu, “Commissioning procedures of the 10 MW high temperature gas-cooled reactor-test module,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 241–247, 2002. View at Publisher · View at Google Scholar · View at Scopus
  6. F. Li, Z. Yang, Z. An, and L. Zhang, “The first digital reactor protection system in China,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 215–225, 2002. View at Publisher · View at Google Scholar · View at Scopus
  7. S. Zhong, S. Hu, M. Zha, and S. Li, “Thermal hydraulic instrumentation system of the HTR-10,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 199–208, 2002. View at Publisher · View at Google Scholar · View at Scopus
  8. M. Yao, Z. Huang, C. Ma, and Y. Xu, “Simulating test for thermal mixing in the hot gas chamber of the HTR-10,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 233–240, 2002. View at Publisher · View at Google Scholar · View at Scopus
  9. M. Zha, S. Zhong, R. Chen, and S. Li, “Temperature measuring system of the in-core components for Chinese 10 MW High Temperature Gas-Cooled Reactor,” Journal of Nuclear Science and Technology, vol. 39, no. 10, pp. 1086–1093, 2002. View at Publisher · View at Google Scholar · View at Scopus
  10. Z. Gao and L. Shi, “Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 51–64, 2002. View at Publisher · View at Google Scholar · View at Scopus
  11. Z. Gao and L. Shi, “Thermal hydraulic transient analysis of the HTR-10,” Nuclear Engineering and Design, vol. 218, no. 1–3, pp. 65–80, 2002. View at Publisher · View at Google Scholar · View at Scopus
  12. F. Chen, Z. Zhang, Y. Zheng, F. Li, Y. Dong, and X. Chen, “Current status of the code validation work using the HTR-10 test data,” in Proceedings of the 5th International Topical Meeting on High Temperature Reactor Technology (HTR '10), Prague, Czech Republic, October 2010.