Abstract
China Fusion Engineering Test Reactor is an “ITER-like” superconducting tokomak reactor. It’s necessary to assess the neutronics parameters, such as tritium breeding ratio, neutron wall loading and nuclear heating of the Water Cooled Solid Breeder (WCSB) blanket for its initial design. In this paper, the neutronics calculations were performed by using MCNP/4C code with the Fusion Evaluated Nuclear Data Library FENDL-2.0. The results show that the neutronics parameters can meet the engineering design requirement. Different source models affect the magnitude and distribution of the neutron wall loading and the nuclear heating were also discussed. The activation calculations were carried out by using FISPACT-2007 with the EAF-2007 library. Activity, afterheat and dose rate of the blanket form the beginning of shutdown to 106 years were presented. The results show that at shutdown the total activity of the equatorial outboard blanket module is 7.27 × 1016 Bq, and the total afterheat is 11.52 kW. These results will provide useful indications for further optimization of the WCSB blanket.
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References
W. Yuanxi, Mission of CFETR, in: ITER Training Forum & Second Workshop on MFE Development Strategy, Hefei, 6 Sept (2012)
MCNP/4C-Monte Carlo N-Particle Transport Code, Los Alamos National Laboratory, CCC-700, (2000)
R.A. Forrest, FISPACT-2007: User Manual, UKAEA Fusion, Report UKAEA FUS534, (2007)
R.A Forrest, J. Kopecky, J.C. Sublet, The European Activation File: EAF-2007 neutron-induced cross section library[M]. EURATOM/UKAEA Fusion Association, 2007
Y. Chen, Y. Wu, Effect of fusion neutron source numerical models on neutron wall loading in a D-D tokamak device. Plasma Sci. Technol. 15, 2 (2003)
W. Yican, Y. Chen, Q. Huang, B. Liu, X. Zhu, M. Kong, L. Caro, Analysis on nuclear heating in the superconducting coils of HT-7U tokamak fusion device. Fusion Eng. Des. 66–68, 1013–1017 (2003)
C. Fausser, A.L. Puma, F. Gabriel, R. Villari, Tokamak D-T neutron source models for different plasma physics confinement modes. Fusion Eng. Des. 87, 787–792 (2012)
J.R. Han, Y.X. Chen, S.H. Yang, X.B. Ma, K.M. Feng, Three-dimensional Monte Carlo neutronic calculations of China ITER HCSB-TBM. Fusion Eng. Des. 83, 720–724 (2008)
J.R. Han, Y.X. Chen, R. Han, K.M. Feng, R.A. Forrest, Activation analysis and waste management of China ITER helium cooled solid breeder test blanket module. Fusion Eng. Des. 85, 761–765 (2010)
P. Rocco, M. Zucchetti, Management strategy to reduce the radioactive waste amount in fusion. J. Fusion Energy 16, 141–148 (1997)
P. Chiovaro, P.A. Di Maio, V. Parrinello, Nuclear analysis of an ITER blanket module. J. Fusion Energy 32(6), 600–606 (2013)
Acknowledgments
The work was supported by National Natural Science Foundation of China (No. 11175201), National science and Technology Major Project (2011ZX06004-024-003), National special project for magnetic confined nuclear fusion energy (2013GB108004) and Program for New Century Excellent Talents in University (NCET-11-0631).
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Li, X., Chen, Y., Tian, Y. et al. Preliminary Neutronics and Activation Analysis of the Water Cooled Solid Breeder Blanket for CFETR. J Fusion Energ 34, 256–260 (2015). https://doi.org/10.1007/s10894-014-9797-z
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DOI: https://doi.org/10.1007/s10894-014-9797-z