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Proceedings Paper

Calculation of neutron streaming effects through the ports of the ITER fusion reactor
Author(s): Massimo Rapisarda; P. Batistoni
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Paper Abstract

The insertion of ports, for diagnostics and additional heating devices, in the vacuum vessel of the projected fusion test reactor ITER will decrease the shielding capacity of the structure, increasing the expected neutron flux in critical components such as the superconducting toroidal field coils. A study of the nuclear heating in the coils has been carried out with the Monte Carlo code MCNP. A complete 45 degree sector of the torus, including the blanket, the vessel and the prot has been modelled. In operating conditions, the ports will be closed with plugs filling the entire hole except for the apertures needed for the particular diagnostic. In the present work, we have considered the pre-collimator plug for the neutron camera diagnostic, a multicollimator for neutron flux detectors and spectrometers located outside the machine. The toroidal coil has been divided in a matrix type shape to calculate the nuclear heating in different layers. Results show that the increase of heating in the more exposed regions is substantial, due both to less shielding thickness and to neutron streaming. Since the bulk structure of the plug can be considered rather typical, the conclusion is that care must be taken in its design and that he possibility to reduce the size of the apertures in the shielding blanket should be taken into account.

Paper Details

Date Published: 27 February 1997
PDF: 4 pages
Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); doi: 10.1117/12.267956
Show Author Affiliations
Massimo Rapisarda, ENEA (Italy)
P. Batistoni, ENEA (Italy)

Published in SPIE Proceedings Vol. 2867:
International Conference Neutrons in Research and Industry
George Vourvopoulos, Editor(s)

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