Title :
Neutronics instrumentation for the European TBM in ITER
Author :
Klix, Axel ; Angelone, M. ; Fischer, Ulrich ; Gehre, Daniel ; Kleizer, Gabor ; Lyoussi, A. ; Ruecker, Tom ; Rovni, Istvan ; Szalkai, Dora
Author_Institution :
Karlsruhe Inst. of Technol., Eggenstein-Leopoldshafen, Germany
Abstract :
Test Blanket Modules (TBM) will be installed in the ITER with the aim to investigate the nuclear performance of different breeding blanket designs for fusion power reactors. Here we present an overview of our ongoing work on three types of neutron flux monitors under development at KIT for the TBMs. A foil activation system with pneumatic sample transport was constructed by KIT utilizing the intense DT neutron generator of Technical University of Dresden. It is used as a test bench for the development of a neutron activation system for the TBMs. Self-powered neutron detectors (SPND) are widely applied in fission reactor monitoring, and the commercially available SPNDs are sensitive to thermal neutrons. We are investigating novel materials for SPND which would be sensitive also to the fast neutron flux expected in the TBMs. Within the I_SMART project, funded by KIC InnoEnergy, KIT is developing an online detector based on silicon carbide electronics for the TBMs.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor fuel; fusion reactor instrumentation; plasma toroidal confinement; tritium handling; European TBM; I SMART project; ITER; KIC InnoEnergy; TBM neutron activation system; Technical University of Dresden; breeding blanket designs; fast neutron flux; foil activation system; fusion power reactors; intense DT neutron generator; neutron flux monitors; neutronics instrumentation; pneumatic sample transport; self-powered neutron detectors; silicon carbide electronics; test bench; test blanket modules; thermal neutrons; tritium breeding blanket; Detectors; Europe; Instruments; Neutrons; Production; Silicon carbide; Temperature measurement; ITER TBM; Test Blanket Module; neutronics instrumentation; tritium production rate;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635492