Engineering design of the ITER invessel neutron monitor using micro-fission chambers
Autor: | Takeo Nishitani, M. Izumi, Michinori Yamauchi, Atsuro Hayakawa, Yoshinori Kusama, Takashi Kondoh, K. Ebisawa |
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Rok vydání: | 2007 |
Předmět: |
Neutron transport
Materials science Tokamak Physics::Instrumentation and Detectors Mechanical Engineering Nuclear engineering Heat transfer coefficient Blanket Fusion power Thermal conduction law.invention Nuclear physics Nuclear Energy and Engineering Nuclear fission law Electromagnetic shielding General Materials Science Nuclear Experiment Civil and Structural Engineering |
Zdroj: | Fusion Engineering and Design. 82:1192-1197 |
ISSN: | 0920-3796 |
Popis: | An invessel neutron monitor using micro-fission chambers is one of the most important diagnostics to measure the fusion power in ITER. A single micro-fission chamber with 10 mg of 235 U to be installed in a gap between a shielding blanket module and a vacuum vessel can cover the range of the fusion power from 100 kW to 1 GW. For the low fusion power operation including D–D operation, a micro-fission chamber bundle consisting of 13 micro-fission chamber units has been designed. Nuclear heating of the micro-fission chamber for high power operations and the micro-fission chamber bundle for low power operation were analyzed by neutron transport calculations using the MCNPX code. Heat transport analyzes for the micro-fission chambers were carried out with a general purpose Finite Element Method code ANSYS 8.1, which indicated that the detector temperature might be kept less than the operational temperature limit by the thermal conduction to the vacuum vessel with the heat transfer coefficient of 100 W/m 2 K or larger. |
Databáze: | OpenAIRE |
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