Abstract
In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium–tritium fusion power reactor using Monte Carlo MCNPX is done. To this end Li4SiO4 was considered as the blanket module. In order to improve the distribution of power density in the blanket module, an arrangement of the neutron multiplier Be in the breeding zone has been optimized. Total TBR of 1.14 is achieved. Finally helium cooled pebble bed was designed as cooling system using COMSOL Multiphysics simulator.
Similar content being viewed by others
References
D. McMorrow, Tritium, JSR-11-345, DOE Office of Fusion Energ. Sci., 2011
M.V. Alenina, V.P. Kolotov, and Yu.M. Platov1, Investigation of lithium carbide as tritium breeding material for blanket of the fusion reactor, Baikov Institute of Metallurgy and Material Science. Russ. Acad. Sci.
J.P. Freidberg, Plasma Physics and Fusion Energy (Cambridge University Press, Cambridge, 2007)
A. Hançerlioğulları,The use of MCNP code in APEX fusion reactor technology, Kastamonu University, Kastamonu Arts & Sciences Faculty, Physics Dept. 37100 Kastamonu, Turkey
D.B. Pelowitz, MCNPX user’s manual, Version 2.6, Apr 2008
A. Choudhary, Synthesis and Characterization of Lithium Silicate Ceramic for the Test Blanket Module (TBM) in Fusion Reactors (National Institute of Technology, Uttarakhand, 2012)
M.E. Sawan, M.A. Abdou, Physics and technology condition for attaining tritium self sufficiency for D–T fuel cycle. Fusion Eng. Des. 81, 1131–1144 (2006)
D. Mc Morrow, Tritium, The MITRE Corporation 7515 Colshire Drive 983-6997 Nov 2011
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Zandi, N., Sadeghi, H., Habibi, M. et al. Blanket Simulation and Tritium Breeding Ratio Calculation for ITER Reactor. J Fusion Energ 34, 1365–1368 (2015). https://doi.org/10.1007/s10894-015-9970-z
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10894-015-9970-z