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Neutron shielding efficiency is mainly related to atomic composition of composites like concrete. Fast neutron attenuation is primarily governed by neutron moderation through light elements, particularly hydrogen, whereas thermal neutron absorption depends on the absorption characteristics of individual nuclei. In this paper the measurements by different methods of hydrogen content in ordinary dolomite concrete OC and heavy-weight magnetite concrete MC designed for International Fusion Materials Irradiation Facility – DEMO-Oriented Neutron Source (IFMIF-DONES) have been presented. Based on the results, neutron shielding parameters were calculated and compared with those of concretes developed for ITER, an international fusion energy research project. The results showed that the relative hydrogen content in MC was lower than in OC. However, the higher density and increased iron (Fe) content resulting from the use of magnetite aggregate yielded more favorable neutron-shielding characteristics for MC. The results also indicate that the optimized IFMIF-DONES concretes offer improved neutron shielding potential compared with the reference ITER concretes.
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Piotrowski et al. (2026) studied this question.
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