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Development of fusion blanket technology for the DEMO reactor

Research output: Contribution to journalJournal article

Published

Journal publication date07/2012
JournalApplied Radiation and Isotopes
Journal number7
Volume70
Number of pages3
Pages1370-1372
Original languageEnglish

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.