DocumentCode :
3775520
Title :
Development of neutronics model for the K-DEMO water cooled ceramic breeder blanket with MCNP code
Author :
J. S. Park;K. Im;S. Kwon
Author_Institution :
DEMO Technology Division, National Fusion Research Institute, Daejeon, Korea
fYear :
2015
fDate :
5/1/2015 12:00:00 AM
Firstpage :
1
Lastpage :
5
Abstract :
During the conceptual design study on the Korean fusion demonstration reactor (K-DEMO) featured by high magnetic field (BT0 = 7.4 T), R=6.8 m, a=2.1 m, and a steady-state operation [1,2], the 3D neutronics models have been developed to evaluate the main parameters such as neutron wall load (NWL) distribution, tritium breeding ratio (TBR) and nuclear heating. To perform neutronics analysis, 3D global models were created from the CAD program (Pro-Engineer™) and imported into the integrated interface program by the help of Monte Carlo Automatic Modeling system (MCAM) to produce input files for the Monte Carlo neutron photon transport code (MCNP) analyses. The appropriate K-DEMO neutronics model configuration, proper shield thickness and assembly gaps between blanket modules were verified based on the comparative study of Monte Carlo analysis results. After comparison of neutronics analysis results, it is shown that the global TBR was slightly different depending on the gap between blanket modules and the nuclear heating in TF coils was proportional to thickness of gap between blanket modules. In the neutron wall loading calculation, the peaks at inboard and ouboard blanket first walls are 3.18 and 3.93 MW/m2 respectively.
Keywords :
"Neutrons","Solid modeling","Heating","Coils","Analytical models","Load modeling","Monte Carlo methods"
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2015 IEEE 26th Symposium on
Electronic_ISBN :
2155-9953
Type :
conf
DOI :
10.1109/SOFE.2015.7482298
Filename :
7482298
Link To Document :
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