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Ignitor is a proposed high magnetic field tokamak aimed at reaching ignition conditions in a plasma of deuterium-tritium and at studying the physics of an ignited plasma for a period of a few seconds. Calculations of neutron and gamma fluxes have been performed, using both ANISN and MCNP codes. Particular care was taken for the zones closer to the plasma and for the components more prone to be affected by radiation damage. Given the calculated gamma and neutron fluxes, the integrated doses have been computed, using the SHAMSI library. Neutron damage on the first wall and vacuum vessel is very small, both in terms of total dpa and of gas production. Due to the small fluence, Ignitor components appear to have no problems of neutron damage. The toroidal magnet insulator is the only material for which the estimated damage is comparable with the maximum limit.

Additional information

Authors: ROLLET S, ENEA, Centro Ricerche Energia Frascati, Roma (IT);BATISTONI P, ENEA, Centro Ricerche Energia Frascati, Roma (IT);ZUCCHETTI M, Politecnico di Torino, Dipartimento di Energetica (IT)
Bibliographic Reference: Paper presented: Sixth International Conference on Fusion Reactor Materials, Stresa (IT), September 27 - October 1, 1993
Availability: Available from (1) as Paper EN 37764 ORA
Record Number: 199311262 / Last updated on: 1994-11-29
Original language: en
Available languages: en
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