Requirements for ITER diagnostics Page: 2 of 20
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Fig. 1. Cross-sectional view at the mid-plane of a port.
II. ITER: The Device. Plasma Parameters and its Program
An evelation view of the ITER device is shown in Fig. 1. This figure shows
two views, one at the midplane of a toroidal field coil, the other at the midplane
between coils. It clearly show the main field coils, both toroidal and poloidal, the
vacuum vessel structure and shielding and blanket structure inside the vacuum
boundary. Protective tiles are mounted on the inner faces of the blanket modules which
can be exchanged through large top ports, lower ports being allocated for vacuum
pumping. The plasma is strongly elongated vertically and will normally operate in a
diverted double-null configuration. The heat-loads and disruption loads for the divertor
tiles provide one of the most difficult engineering problems for ITER and they are
presently identified as being made of high-Z material /2/.
The principal parameters of the device are given in Table 1 and representative
plasma parameters are given in Table 2. A number of reference operational pulses have
been developed /2,3/ ranging from a relatively short "ignition" scenario to the nominal
steady-state, the preferred mode for the engineering test program during the technology
phase of the experiments. A long-pulse, non-inductive current-driven controlled-burn,
is perhaps the most probable mode. The initial physics phase of the operation will be
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Young, K.M. Requirements for ITER diagnostics, article, January 1, 1991; New Jersey. (https://digital.library.unt.edu/ark:/67531/metadc1054270/m1/2/: accessed April 21, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.