Blanket diagnostics system for ITER

• Published in: Fusion engineering and design Vol. 39; no. Pt A; pp. 775 - 780
• Main Authors: Epinatiev, A., Razmerov, A., Prozorov, V., Ovchinnikov, V.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01-09-1998
• Subjects: Experimental reactors; Fusion reactors; Magnetic field effects; Neutron irradiation; Thermocouples; Tokamak devices
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/S0920-3796(98)00228-2

Measurement and diagnostics system for the fusion experimental reactor ITER blanket is discussed in this paper. Diagnostics are proposed to be carried out in three directions: thermalhydraulic parameter measurement; neutron characteristic measurement; and structural metal condition control. The considered system ensures reactor maintenance safety at all regimes, provides the required blanket structure operation life-time by conducting regular measurements and solves scientific experiment tasks. Much attention has been given to thermalhydraulic parameter measurements since they are considered important for reactor for reactor maintenance safety, for structural metal condition control and for instrumentation, for scientific experiments. Thermalhydraulic parameter measurements are also regarded as an ancillary tool for other diagnostics method implementation and mutual checking-up with other diagnostics. How magnetic fields affect the results of thermal parameter measurements when thermocouples are used is discussed.