Safe irradiated nuclear fuel (INF) storage of research reactors is ensured by solving issues of protection against γ-irradiation while the neutron component is usually without consideration due to significantly lower intensity. Regarding the low-enriched composite uranium fuel of the IVG.1M reactor that is characterized by a set of elements with low and mean atomic weight where reaction is possible (α, n), evaluation of the neutron component is an indispensable procedure for ensuring radiation safety INF storage.
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