If you read this message your browser is not standard !
although this site is perfectly accessible from any browser, some functionalities
are visible only with browsers respecting "W3C consortium" standards.

ENEA - Fusion division

Header with ENEA, FUSION and EURATOM logos

You are in: Home » Research Activities » Fusion Technologies » Neutronics » details


Neutron Transport Calculations

Model of a sector of ITER Model of a sector of ITER designed with the
MCNP neutron transport code.

Calculations of neutron and photon transport are very important as support to the experimental activity. They serve as a calibration and design instrument for diagnostics and are essential during the design phase of the components of next-generation fusion reactors.

At present, the calculations can be completely relied on to establish the shielding thickness necessary to fulfil safety requirements relative to doses released outside the reactor or relative to the energy liberated on superconducting magnets.

The calculations have to be absolutely reliable, so instruments that permit a detailed description of the geometry (for example, the neutron transport code MCNP, see figure) are used.