Colling, Bethany R and Monk, Stephen David (2012) Development of fusion blanket technology for the DEMO reactor. Applied Radiation and Isotopes, 70 (7). pp. 1370-1372. ISSN 0969-8043Full text not available from this repository.
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.
|Journal or Publication Title:||Applied Radiation and Isotopes|
|Uncontrolled Keywords:||Fusion ; Tritium ; Lithium ; DEMO ; Energy|
|Subjects:||T Technology > TA Engineering (General). Civil engineering (General)|
|Departments:||Faculty of Science and Technology > Engineering|
|Deposited On:||16 Dec 2011 09:06|
|Last Modified:||29 Mar 2017 04:28|
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