Abstract
The design work of China Fusion Engineering Test Reactor (CFETR) has been started since 2012. In past years, the physical parameters and related engineering design of subsystems were modified, evaluated and redesigned for several rounds in order to fulfill the final scientific goals. Remote maintenance (RM) is identified as one of the key issues of the CFETR because of the neutron activation of the in-vessel components. Different schemes were proposed and comparatively assessed to reach the best possible tradeoff between RM strategies and Tokamak machine designs. This paper will give an overall introduction of the latest version of RM strategy and system conceptual design based on current physical configuration with 16 toroidal field coils and larger sizes. In general, modular blanket components will be removed through only two large vertical maintenance ports while two lower horizontal ports are employed for divertor removing. The work has also provided guidelines for compatibility consideration such as the blanket and divertor modularity, the cryostat pipe arrangement, and the corridor layout to hot cell. In addition, some innovative RM system design for the blanket and divertor maintenance was also provided in the paper, such as the implementation of a toroidal mover transferring blankets to vertical ports, and the novel cask design ensuring storing six divertor at the same time.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
J. Li, Y. Wan, Present state of Chinese magnetic fusion development and future plans. J. Fusion Energy 7, 1–12 (2018)
Y.T. Song, S.T. Wu, J.G. Li et al., Concept design of CFETR tokamak machine. IEEE Trans. Plasma Sci. 42(3), 503–509 (2014)
Y. Song, S. Wu, Y. Wan et al., Concept design on RH maintenance of CFETR Tokamak reactor. Fusion Eng. Des. 89(9–10), 2331–2335 (2014)
Z. Zhou, D. Yao, P. Zi, The research activities on remote handling system for CFETR. J. Fusion Energy 34(2), 232–237 (2015)
J. Zheng, Y. Song, K. Lu et al., Overview of the design status of superconducting magnet system of CFETR. IEEE Trans. Appl. Supercond. 28, 1–5 (2018)
J. Wei, Y. Song, K. Pei et al., Conceptual design of Blanket remote handling system for CFETR. Fusion Eng. Des. 100, 190–197 (2015)
Manfen Han, Yantao Song, Yong Cheng et al., Concept design of Water hydraulic circuit for manipulator of CFETR Blanket maintenance. J. Fusion Energy 34(4), 765–768 (2015)
W. Zhao, Y. Song, H. Wu et al., Concept design of the CFETR divertor remote handling system. Fusion Eng. Des. 98, 1706–1709 (2015)
R. Haange, ITER Joint Central Teams, ITER Home, Remote handling maintenance of ITER. Nucl. Fusion 39(11Y), 2043–2050 (1999)
G. Di Gironimo, C. Labate, F. Renno et al., Concept design of divertor remote handling system for the FAST machine. Fusion Eng. Des. 88(9–10), 2052–2056 (2013)
E. Villedieu, Y.T. Song, Y. Cheng et al., Tokamak design and maintenance scheme tradeoff application on CFETR. IEEE Trans. Plasma Sci. 46(5), 1156–1165 (2018)
Y. Wan, J. Li, Y. Liu et al., Overview of the present progress and activities on the CFETR. Nucl. Fusion 57(10), 102009 (2017)
L. Cao, D. Yao, Z. Zhou, Availability analysis for CFETR. J. Fusion Energy 33(5), 523–528 (2014)
C.H. Choi, A. Tesini, R. Subramanian et al., Multi-purpose deployer for ITER in-vessel maintenance. Fusion Eng. Des. 98, 1448–1452 (2015)
M.S. Manuelraj, P. Dutta, K.K. Gotewal et al., Structural analysis of ITER multi-purpose deployer. Fusion Eng. Des. 109, 1296–1301 (2016)
H. Pan, K. He, Y. Cheng et al., Conceptual design of EAST multi-purpose maintenance deployer system. Fusion Eng. Des. 118, 25–33 (2017)
Y. Perrot, J.J. Cordier, J.P. Friconneau et al., ITER articulated inspection arm (AIA): R&d progress on vacuum and temperature technology for remote handling. Fusion Eng. Des. 75, 537–541 (2005)
S. Shi, Y. Song, Y. Cheng et al., Conceptual design and main progress of EAST articulated maintenance arm (EAMA) system. Fusion Eng. Des. 104, 40–45 (2016)
S. Shi, H. Wu, Y. Song et al., Mechanical design and error prediction of a flexible manipulator system applied in nuclear fusion environment. Ind. Robot Int. J. 44(6), 711–719 (2017)
J. Keep, S. Wood, N. Gupta et al., Remote handling of DEMO breeder blanket segments: Blanket transporter conceptual studies. Fusion Eng. Des. 124(Nov.), 420–425 (2017)
C. González Gutiérrez, C. Damiani, M. Irving et al., ITER transfer cask system: status of design, issues and future developments. Fusion Eng. Des. 85(10–12), 2295–2299 (2010)
Acknowledgements
This work was supported by National Natural Science Foundation of China (No.11802305) and the major special projects of the Ministry of Science and Technology, China, No. 2017YFE0300503). We also deeply thank to the Shenzhen Clean Energy Research Institute and all the members of CFETR design team for their hard work and beneficial discussions.
Author information
Authors and Affiliations
Corresponding author
Additional information
Publisher's Note
Springer Nature remains neutral with regard to jurisdictional claims in published maps and institutional affiliations.
Rights and permissions
About this article
Cite this article
Zhao, W., Shi, S., Cheng, Y. et al. Strategy Study and Preliminary Conceptual Design of the Remote Maintenance Systems for in Vessel Components of CFETR. J Fusion Energ 39, 67–76 (2020). https://doi.org/10.1007/s10894-020-00237-6
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10894-020-00237-6