Neutron Transport Calculations for ITER
37th Annual CNS-CNA Student Conference - 2013 June 11


Presented at:
37th Annual CNS-CNA Student Conference
2013 June 11
Location:
Toronto, Canada
Session Title:
Student Conference Session

Authors:
Savino Longo (McMaster University)
Adriaan Buijs (McMaster University)
  

Abstract

With the development of the upcoming fusion 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. The distribution of neutrons in a fusion reactor obey a diffusion equation that is very similar to that of a fission reactor. As demonstrated in fission reactor analysis, the terms in the diffusion equation can be divided into Production, Leakage, Scattering and Absorption. In this analysis, the upcoming fusion reactor ITER is evaluated using these four neutron interactions to predict how the components of the reactor will interact with the high energy fusion neutrons. Simulations calculating the neutron flux were done by solving the diffusion equation numerically for a 2D cross-sectional mesh of the dimensions of the ITER tokamak.

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