Skip to main content
SpringerLink
Log in

RAMI Analysis of HCCB TBS for ITER

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

Abstract

ITER is the first worldwide international experimental nuclear fusion facility, which aims to prove the physics and technological basis for future fusion power plants. As main stages of ITER technical risk control, the reliability, availability, maintainability and inspectability (RAMI) approach should be applied to all ITER components during their design phase to reduce potential technical risks. Test blanket modules play a key role in ITER. Helium cooled ceramic breeder (HCCB) TBM is one of TBM concepts which were proposed by China. HCCB TBM and its ancillary system are called HCCB test blanket system (TBS). The RAMI analysis was performed on the conceptual design of the ITER HCCB TBS in this paper. A functional breakdown was prepared in a bottom-up approach, resulting in the system being divided into 3 main functions, 1 support function, 14 sub-functions and 50 basic functions. These functions were described using the IDEF0 method. Reliability block diagrams were prepared to estimate the reliability and availability of each function under the stipulated operating conditions. The inherent availability of the HCCB TBS expected after implementation of mitigation actions was calculated to be 94.69 % over 2 years. A failure modes, effects and criticality analysis was performed with criticality charts highlighting the risk level of the different failure modes with regard to their probability of occurrence and their effects on the availability.

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

Similar content being viewed by others

References

  1. J.N. Holtkamp, An overview of the ITER project. Fusion Eng. Des. 82, 427–434 (2007)

    Article  Google Scholar 

  2. D. van Houtte, K. Okayama, F. Sagot, RAMI approach for ITER. Fusion Eng. Des. 85, 1220–1224 (2010)

    Article  Google Scholar 

  3. S. Kitazawa, K. Okayama, Y. Neyatani et al., RAMI analysis of ITER CODAC. Fusion Eng. Des. 87, 1510–1513 (2012)

    Article  Google Scholar 

  4. Y. Wu, FDS Team, Conceptual design activities of FDS series fusion power plants in China. Fusion Eng. Des. 81(23–24), 2713–2718 (2006)

    Article  Google Scholar 

  5. Y. Wu, FDS Team, Conceptual design, testing strategy of a dual functional lithium lead test blanket module for ITER and EAST. Nucl. Fusion 47, 1533–1539 (2007)

    Article  ADS  Google Scholar 

  6. Y. Wu, FDS Team, Conceptual design activities of FDS series fusion power plants in China. Fusion Eng. Des. 81, 2713–2718 (2006)

    Article  Google Scholar 

  7. Y. Wu, FDS Team, Conceptual design of the china fusion power plant FDS-II. Fusion Eng. Des. 83(10–12), 1683–1689 (2008)

    Article  Google Scholar 

  8. Q. Huang, C. Li, Y. Li et al., Progress in development of China low activation martensitic steel for fusion application. J. Nucl. Mater. 367–370, 142–146 (2007)

    Article  Google Scholar 

  9. Y. Wu, Q. Huang, Z. Zhu et al., R&D of dragon series lithium lead loops for material and blanket technology testing. Fusion Sci. Technol. 62, 272–275 (2012)

    Google Scholar 

  10. Y. Wu, Design status and development strategy of China liquid lithium–lead blankets and related material technology. J. Nucl. Mater. 367–370, 1410–1415 (2007)

    Article  Google Scholar 

  11. Y. Wu, J. Qian, J. Yu, The fusion-driven hybrid system and its material selection. J. Nucl. Mater. 307–311, 1629–1636 (2002)

    Article  MATH  Google Scholar 

  12. Y. Wu, J. Jiang, M. Wang, M. Jin et al., A fusion-driven subcritical system concept based on viable technologies. Nucl. Fusion 51, 103036 (2011)

    Article  ADS  Google Scholar 

  13. L. Hu, R. Yuan, H. Chen et al., Failure modes and effects analysis on ITER DFLL-TBM system. Fusion Eng. Des. 87, 1307–1309 (2012)

    Article  Google Scholar 

  14. D. van Houtte, K. Okayama, F. Sagot, ITER operational availability and fluence objectives. Fusion Eng. Des. 86, 680–683 (2011)

    Article  Google Scholar 

  15. Component reliability data for use in probabilistic safety assessment, IAEA-TECDOC-478, 1988

  16. Cadwallader LC, Selected component failure rate values from fusion safety assessment tasks, INEEL/EXT-98-00892, 1998

  17. Abdou M, Next steps for realizing fusion power and comparative analysis of roadmaps of word major fusion programs. TOFF 2012 ANS 20th topical meeting on the technology of fusion energy (Nashville, TN, 2012)

Download references

Acknowledgments

This work was supported by the Strategic Priority Research Program of Chinese Academy of Sciences (No. XDA03040000), the National Special Program for ITER (Nos. 2014GB112001 and 2014GB116000), the Informatizational Special Projects of Chinese Academy of Sciences (No. XXH12504-1-09), and the Foundation of President of Hefei Institutes of Physical Science (No. YZJJ201327). The author expresses his appreciation and gratitude for the other members of FDS team. Thanks for their contributed to this work.

Author information

Authors and Affiliations

  1. Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, 230031, Anhui, China

    Dagui Wang, Jin Wang, Run Yuan, Miao Nie & Fang Wang

Authors
  1. Dagui Wang
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Jin Wang
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Run Yuan
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Miao Nie
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. Fang Wang
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Fang Wang.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Wang, D., Wang, J., Yuan, R. et al. RAMI Analysis of HCCB TBS for ITER. J Fusion Energ 34, 1094–1099 (2015). https://doi.org/10.1007/s10894-015-9913-8

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10894-015-9913-8

Keywords

Search

Navigation