Skip to main content
SpringerLink
Log in

Reliability Data Analysis for Tritium Extraction System Pipes of CN HCCB TBM

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

Abstract

A tritium extraction system (TES) is one of important ancillary systems of the China helium cooled ceramic breeder test blanket module (CN HCCB TBM). The high reliability and availability of TES will be needed for safety operation of circulation and processing of tritium purge gas. Probabilistic Safety Assessment (PSA) and reliability, availability, maintainability, inspectability (RAMI) analysis of the TES should be performed during the design phase according to the CN HCCB TBM plan. Accurate reliability data is required to provide meaningful results for PSA and RAMI analysis. Since there is no TES pipes failure rate data available from fusion operating experiences. Therefore, it is necessary to use the existing pipe operating experiences to calculate component failure rates of the TES pipes. In this paper, the k factor method was used to adjust the failure rates of the TES pipes under the different environments and conditions by combining physics of failure models and a conservative estimation technique. The failure rates of the TES can provide references for the optimization of TES pipes design and data support for PSA and RAMI analysis of the TES.

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

Similar content being viewed by others

References

  1. Z. Long, T. Luo, K. Feng, Conceptual design on interface between ITER and tritium extraction system of Chinese helium-cooled solid breeder test blanket module. Fusion Eng. Des. 85, 2213–2216 (2010)

    Article  Google Scholar 

  2. K.M. Feng, C.H. Pan, G.S. Zhang et al., Progress on solid breeder TBM at SWIP. Fusion Eng. Des. 85, 2132–2140 (2010)

    Article  Google Scholar 

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

    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. L. Qiu, Y. Wu, B. Xiao et al., A low aspect ratio tokamak transmutation system. Nucl. Fusion 40, 629–633 (2000)

    Article  ADS  Google Scholar 

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

    Article  Google Scholar 

  7. Y. Wu, J. Jiang, M. Wang et al., A fusion-driven subcritical system concept based on viable technologies. Nucl. Fusion 51(10), 103036 (2011)

    Article  ADS  Google Scholar 

  8. 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 

  9. Y. Wu, FDS Team, Fusion-based hydrogen production reactor and its material selection. J. Nucl. Mater. 386–388, 122–126 (2009)

    Article  Google Scholar 

  10. L. Hu, Y. Wu, Probabilistic safety assessment of the dual-cooled waste transmutation blanket for the FDS-I. Fusion Eng. Des. 81, 1403–1407 (2006)

    Article  Google Scholar 

  11. Y. Wu, FDS Team, Conceptual design and testing strategy of a dual functional lithium–lead test blanket module in ITER and EAST. Nucl. Fusion 47(11), 1533–1539 (2007)

    Article  ADS  Google Scholar 

  12. Y. Wu, FDS Team, Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER. Fusion Eng. Des. 82, 1893–1903 (2007)

    Article  Google Scholar 

  13. Y. Wu, FDS Team, Development of reliability and probabilistic safety assessment program riskA. Ann. Nucl. Energy. (2015). doi:10.1016/j.anucene.2015.03.020

    Google Scholar 

  14. F. Wang, Y. Chen, X. Ye, et al., System Design Description for Conceptual Design of China Helium Cooled Ceramic Breeder Test Blanked System (CN HCCB TBS). Document No. HCCB TBM-SWIP/CNDA/IOCDDD V1.0, pp. 113–117, 2014

  15. D. Wang, J. Wang, R. Yuan et al., RAMI analysis of HCCB TBS for ITER. J. Fusion Energ. (2015). doi:10.1007/s10894-015-9913-8

    Google Scholar 

  16. R. Nyman, S. Erixon, B. Tomic et al., Reliability of Piping System Components Framework for Estimating Failure Parameters from Service Data. SKI 97:26 (Swedish Nuclear Power Inspectorate, Stockholm, 1997)

    Google Scholar 

  17. K. Simola, U. Pulkkinen, H. Talja et al., Comparison of approaches for estimating pipe rupture frequencies for risk-informed in-service inspections. Reliab. Eng. Syst. Saf. 84, 65–74 (2004)

    Article  Google Scholar 

  18. K.N. Fleming, Markov models for evaluating risk-informed in-service inspection strategies for nuclear power plant piping systems. Reliab. Eng. Syst. Saf. 83, 27–45 (2004)

    Article  Google Scholar 

  19. R. Tregoning, L. Abramson et al., Estimating Loss of Coolant Accident (LOCA) Frequencies Through the Elicitation Process. NUREG-1829 (US Nuclear Regulatory Commission, Washington, 2008)

    Google Scholar 

  20. F. Di Maio, D. Colli, E. Zio et al., A Multi-State Physics Modeling approach for the reliability assessment of Nuclear Power Plants piping systems. Ann. Nucl. Energy 80, 151–165 (2015)

    Article  Google Scholar 

  21. E.L. McCabe, W.B. Pearce, G.D. Rise, Method for Developing Equipment Failure Rate K FACTORS. Report D180-17674-2 (Boeing Company, Seattle, 1975)

    Google Scholar 

  22. T.D. Marshall, L.C. Cadwallade, Recommended In-vessel Tubing Failure Rates for the International Thermonuclear Experimental Reactor. in 15th IEEE/NPSS Symposium on Fusion Engineering (1993)

  23. B.O.Y. Lydell, Pipe failure probability-the Thomas paper revisited. Reliab. Eng. Syst. Saf. 68, 207–217 (2000)

    Article  Google Scholar 

  24. L.C. Cadwallader, Vacuum Bellows, Vacuum Piping, Cryogenic Break, and Copper Joint Failure Rate Estimates for ITER Deisgn Use. INL/EXT-10-18973 (Idaho National Laboratory, Idaho Falls, 2010)

    Book  Google Scholar 

  25. L.C. Cadwallader, In-Vessel Coil Material Failure Rate Estimates for ITER Design Use. INL/EXT-13-28031 (Idaho National Laboratory, Idaho Falls, 2013)

    Book  Google Scholar 

  26. L. C. Cadwallader, Failure Rate Adjustment Factors for High Technology Components. in 25th Symposium on Fusion Engineering (2013)

  27. W. Fa, Safety Analysis of TBM Tritium System (China Academy of Engineering Physics, Chendu, 2012). (in Chinese)

    Google Scholar 

  28. J.L. Woodward, R. Pitbaldo, LNG Risk Based Safety: Modeling and Consequence Analysis (Wiley, New Jersey, 2010), pp. 57–58

    Book  Google Scholar 

  29. O. Haillant, D. Dumbleton, A. Zielnik, An Arrhenius approach to estimating organic photovoltaic module weathering acceleration factors. Sol. Energy Mater. Sol. Cells 95, 1889–1895 (2011)

    Article  Google Scholar 

  30. S. Ciattaglia, G. Cambi et al., Environmental Conditions Room Book. ITER IDM 2UUZ23 (ITER IO, French, 2012)

Download references

Acknowledgments

The authors would like to show their great appreciation to other members in FDS Team for their supports and contributions to this research. Thanks for their contributed to this work. The authors would like to thank Lee Cadwallader for his helpful discussion on this work. This work was supported by National Magnetic Confinement Fusion Science Program of China (Nos. 2014GB112001, 2015GB116001), the Special Program for Informatization of the Chinese Academy of Sciences (No. XXH12504-1-09), and the Foundation of President of Hefei Institutes of Physical Science (No. YZJJ201327).

Author information

Authors and Affiliations

  1. University of Science and Technology of China, Hefei, 230027, Anhui, China

    Miao Nie

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

    Miao Nie, Jiaqun Wang, Jin Wang, Leiming Shang & Fang Wang

Authors
  1. Miao Nie
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Jiaqun Wang
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Jin Wang
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Leiming Shang
    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

Nie, M., Wang, J., Wang, J. et al. Reliability Data Analysis for Tritium Extraction System Pipes of CN HCCB TBM. J Fusion Energ 34, 1378–1384 (2015). https://doi.org/10.1007/s10894-015-9976-6

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10894-015-9976-6

Keywords

Search

Navigation