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Development of fusion blanket technology for the DEMO reactor

Research output: Contribution to journalJournal article

Published

<mark>Journal publication date</mark>07/2012
<mark>Journal</mark>Applied Radiation and Isotopes
Issue7
Volume70
Number of pages3
Pages1370-1372
<mark>Original language</mark>English

Abstract

The viability of various materials and blanket designs for use in nuclear fusion reactors can be tested using computer simulations and as parts of the test blanket modules within the International Thermonuclear Experimental Reactor (ITER) facility. The work presented here focuses on blanket model simulations using the Monte Carlo simulation package MCNPX (Computational Physics Division Los Alamos National Laboratory, 2010) and FISPACT (Forrest, 2007) to evaluate the tritium breeding capability of a number of solid and liquid breeding materials. The liquid/molten salt breeders are found to have the higher tritium breeding ratio (TBR) and are to be considered for further analysis of the self sufficiency timing.