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Report No.
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Advanced neutron shielding material using zirconium borohydride and zirconium hydride

Hayashi, Takao; Tobita, Kenji; Nakamori, Yuko*; Orimo, Shinichi*

Neutron transport calculations have been carried out to assess the capability of zirconium borohydride (Zr(BH$$_{4}$$)$$_{4}$$) and zirconium hydride (ZrH$$_{2}$$) as advanced shield materials, because excellent shields can be used to protect outer structural materials from serious activation. The neutron shielding capability of Zr(BH$$_{4}$$)$$_{4}$$ is lower than ZrH$$_{2}$$, even though the hydrogen density of Zr(BH$$_{4}$$)$$_{4}$$ is slightly higher than that of ZrH$$_{2}$$. High-Z atoms are effective in neutron shielding as well as hydrogen atoms. The combination of steel and Zr(BH$$_{4}$$)$$_{4}$$ can improve the neutron shielding capability. The combinations of (Zr(BH$$_{4}$$)$$_{4}$$ + F82H) and (ZrH$$_{2}$$ + F82H) can reduce the thickness of the shield by 6.5% and 19% compared to (water + F82H), respectively. The neutron flux for Zr(BH$$_{4}$$)$$_{4}$$ is drastically reduced in the range of neutron energy below 100 eV compared to other materials, due to the effect of boron, which can lead to a reduction of radwaste from fusion reactors.

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Category:Materials Science, Multidisciplinary

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