Expected Radiation Levels for Present and Future Tokamaks
スポンサーリンク
概要
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Because of their necessary tight coupling to the plasma by line-of-sight, vacuum and signal intensity requirements, plasma diagnostics are very strongly affected by the radiation environment of a tokamak producing neutrons. This paper summarizes information available from nuclear code calculatons for a number of tokamaks in operation at the moment and being considered in future phase. The two presently operating devices are the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET). The operational philosophy for the diagnostics of these two devices is quite different and this is reflected in the different ways of handling the shielding. Extensive calculations have been carried out for these devices and they will be discussed. In TFTR there is a reduced level of shielding for deuterium operations than for tritium and both cases will be described. For TFTR, where local shielding surrounding individual diagnostics is often required, some examples of the local shielding studies will be given. Two examples of the devices in the planning stage will be given. The first is the INTOR project which is an example of a reactor-like device for which a relatively modest plasma diagnostic set might be expected to operate during its burning phase. The second is a Compact Ignition Tokamak (CIT) under conceptual design in the US for the purpose of studying a small highdensity alpha-particle heated plasmas. This device will therefore require significant diagnosis during the ignition-phase and adequate shielding for the diagnostic areas is therefore a critical requirement. These four devices provide a sufficient information base for consideration of the radiation problems for plasma diagnostics.
- 核融合科学研究所の論文
著者
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Liew S-l.
Princeton Plasma Physics Laboratory
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Young K.
Princeton Plasma Physics Laboratory
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Ku L.
Princeton Plasma Physics Laboratory