Skip to main content
SpringerLink
Log in

Steady State and Transient Analysis of Novel Design Helium Cooled Ceramic Blanket (HCCB) System of China Fusion Engineering Test Reactor (CFETR)

  • Original Research
  • Published:
Journal of Fusion Energy Aims and scope Submit manuscript

Abstract

An upgraded form of China fusion engineering test reactor (CFETR) was investigated for the safety performance. In the current study, modification of the designs were presented with relative tolerance. The steady state were calculated for the new design using Relap5 code. Two accidents were simulated i.e., in-vessel and In-box loss of coolant accident. These accidents were simulated in helium cooled ceramic blanket (HCCB) system for the purpose to investigate the safety measures of the CFETR. It is utmost important to ensure the safety performance of the reactor. In this research, sudden break at blanket system was assumed and calculated different parameters including temperature, pressure and coolant fluxes to observe the differences in pattern during the accident under limited time domain. The research is very important because the design of HCCB is new and there is a need to conduct steady state and transient state of the reactor in order to make sure and authenticate the design and to safer the reactor.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Fig. 1
Fig. 2
Fig. 3
Fig. 4
Fig. 5
Fig. 6
Fig. 7
Fig. 8
Fig. 9
Fig. 10
Fig. 11
Fig. 12
Fig. 13
Fig. 14
Fig. 15
Fig. 16

Similar content being viewed by others

References

  1. Y.T. Song, W.Y. Wu, S.J. Du et al., Tokamak Engineering Mechanics (Springer, Berlin, 2014)

    Book  Google Scholar 

  2. M. Keilhacker, M.L. Watkins, JET, team. D-T experiments in the JET tokamak. J. Nucl. Mater. 266–269, 1–13 (1999)

    Article  ADS  Google Scholar 

  3. S. Ishida, P. Barabaschi, Y. Kamada, The JT-60SA team. Status and prospect of the JT-60SA project. Fusion Eng. Des. 85, 2070–2079 (2010)

    Article  Google Scholar 

  4. J.S. Bak, H.L. Yang, Y.K. Oh et al., Current status of the KSTAR construction. Cryogenics 47, 356–363 (2007)

    Article  ADS  Google Scholar 

  5. M. Lei et al., Process on CFETR HCCB blanket design, ASIPP & PPPL Blanket Integration Design Team Meeting, November 2015. China

  6. I. Ricapito et al., The ancillary systems of the European test blanket modules: configuration and integration in TIER. Fusion Eng. Des. 85, 1154–1161 (2010)

    Article  Google Scholar 

  7. L.V. Boccaccini et al., The EU TBM systems: design and development programme. Fusion Eng. Des. 84, 333–337 (2009)

    Article  Google Scholar 

  8. J. Xuezhou, R. Meyder, Thermal-hydraulic system study of the helium cooled pebble bed (HCPB), blanket module (TBM) for ITER using system Code RELAP5. Plasma Sci. Technol 7(2), 2753 (2005)

    Article  Google Scholar 

  9. L.V. Boccaccini, R. Meyder, X. Jin, Analysis of three LOCAs for the European HCPB test blanket syste. Fusion Eng. Des. 82, 2335–2340 (2007)

    Article  Google Scholar 

  10. Y. Zhang, T. Peng, Modeling TBM components by using Relap5 code. ICONE-21, Paper ID:16304, July 29–August 02, 2013, China

  11. M.Y. Ahn et al., Preliminary safety analysis of korean helium cooled solid breeder test blanket module. Fusion Eng. Des. 83, 1753–1758 (2008)

    Article  Google Scholar 

  12. E. Popov, G.L. Yoder, S.H. Kim, Relap5 model of the first wall/blanket primary heat transfer system, Doc no. US ITER 12101-TD0001-R00. 2010

  13. T. Ihli, T.K. Basu, L.M. Giancarli et al., Review of blanket designs for advanced fusion reactors. Fusion Eng. Des. 83, 912–919 (2008)

    Article  Google Scholar 

  14. RELAP5/MOD3.3 Code Manual Volume., Code Structure, System Models, and Solution Methods, vol. I (Nuclear Safety Analysis Division, Idaho, 2001)

    Google Scholar 

  15. RELAP5/MOD3.3 Code Manual, User’s Guide and Input Requirements, vol. II (Nuclear Safety Analysis Division, Idaho, 2001)

    Google Scholar 

  16. M.J. Wang et al., Thermal hydraulic and stress coupling analysis for AP1000 Pressurized Thermal Shock (PTS) study under SBLOCA scenario. Appl. Thermal Eng. 122, 158–170 (2017)

    Article  Google Scholar 

  17. J.J. Serrano-Aguilera, L. Valenzuela, L. Parras, Thermal hydraulic RELAP5 model for a solar direct steam generation system based on parabolic trough collectors operating in once-through mode. Energy 133, 796–807 (2017)

    Article  Google Scholar 

  18. L. Shuzhou et al., Thermal hydraulic and stress coupling analysis for AP1000 Pressurized Thermal Shock (PTS) study under SBLOCA scenario. Appl. Therm. Eng. 117, 443–451 (2017)

    Article  Google Scholar 

  19. S.U.D. Khan et al., Thermal hydraulic analysis of CFETR during thermal quenching by comparative approach of Relap5 and theatre code. Modern Phys. Lett. B 30(30), 1650357 (2016)

    Article  ADS  Google Scholar 

  20. A. Kaliatka, M. Valincius, Modeling of pipe break accident in a district heating system using RELAP5 computer code. Energy 44, 813–819 (2012)

    Article  Google Scholar 

  21. X.M. Cheng et al., Thermal hydraulic responses of the primary heat transfer system of the WCCB blanket to accident cases for CFETR. Fusion Eng. Des. 121, 50–59 (2017)

    Article  Google Scholar 

  22. Q. Lian et al., Preliminary safety assessment on two LOCAs under ITER-like condition for the optimized CFETR helium cooled solid breeder blanket. Fusion Eng. Des. 121, 235–244 (2017)

    Article  Google Scholar 

Download references

Acknowledgements

The authors would like to sincerely appreciate the Research Center, College of Engineering at King Saud University for its funding of this research.

Author information

Authors and Affiliations

  1. Sustainable Energy Technologies Center, King Saud University, Riyadh, Kingdom of Saudi Arabia

    Salah Ud-Din Khan & Usman Ali Rana

  2. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, People’s Republic of China

    Jian Wang

  3. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, People’s Republic of China

    Yuntao Song

  4. National Tokamak Fusion Program, Pakistan Atomic Energy Commission (PAEC), Islamabad, 3329, Pakistan

    Shahab Ud-Din Khan & Riaz Khan

Authors
  1. Salah Ud-Din Khan
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Jian Wang
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Yuntao Song
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Shahab Ud-Din Khan
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. Usman Ali Rana
    View author publications

    You can also search for this author in PubMed Google Scholar

  6. Riaz Khan
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Salah Ud-Din Khan.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Khan, S.UD., Wang, J., Song, Y. et al. Steady State and Transient Analysis of Novel Design Helium Cooled Ceramic Blanket (HCCB) System of China Fusion Engineering Test Reactor (CFETR). J Fusion Energ 37, 308–316 (2018). https://doi.org/10.1007/s10894-018-0191-0

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10894-018-0191-0

Keywords

Search

Navigation