Research output: Contribution to Journal/Magazine › Journal article › peer-review
Research output: Contribution to Journal/Magazine › Journal article › peer-review
}
TY - JOUR
T1 - Development of fusion blanket technology for the DEMO reactor
AU - Colling, Bethany R
AU - Monk, Stephen David
PY - 2012/7
Y1 - 2012/7
N2 - 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.
AB - 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.
KW - Fusion
KW - Tritium
KW - Lithium
KW - DEMO
KW - Energy
U2 - 10.1016/j.apradiso.2011.11.006
DO - 10.1016/j.apradiso.2011.11.006
M3 - Journal article
VL - 70
SP - 1370
EP - 1372
JO - Applied Radiation and Isotopes
JF - Applied Radiation and Isotopes
SN - 0969-8043
IS - 7
ER -