Neutron Transport Calculations for ITER

Abstract

With the development of the upcoming International Thermonuclear Experimental Reactor (ITER), analysis is being done into the neutron behaviour in a fusion reactor. This is an important consideration for reactor shielding and power production. Many of the neutron analysis techniques used in fission reactors such as multi-group energy approximations and diffusion theory approximations of the neutron transport can still be applied to calculate neutron flux distributions in fusion reactors [1,2]. As demonstrated in fission reactor analysis, the terms in the diffusion equation can be divided into Production, Scattering, Absorption and Leakage terms. Using these four neutron interactions, the neutron behaviour in a fusion reactor can be analyzed.