Neutronics assessment of advanced shield materials using metal hydride and borohydride for fusion reactors

Hayashi, Takao; Tobita, Kenji; Nishio, Satoshi; Ikeda, Kazuki*; Nakamori, Yuko*; Orimo, Shinichi*; DEMO Plant Design Team

Neutron transport calculations were carried out to evaluate the capability of metal hydrides and borohydrides as an advanced shielding material. Some hydrides indicated considerably higher hydrogen content than polyethylene and solid hydrogen. The hydrogen-rich hydrides show superior neutron shielding capability to the conventional materials. From the temperature dependence of dissociation pressure, ZrH $_{2}$ and TiH $_{2}$ can be used without releasing hydrogen at the temperature of less than 640 $^{circ}$ C at 1 atm. ZrH $_{2}$ and Mg(BH $_{4}$ ) $_{2}$ can reduce the thickness of the shield by 30% and 20% compared to a combination of steel and water, respectively. Mixing some hydrides with F82H produces considerable effects in -ray shielding. The neutron and -ray shielding capabilities decrease in order of ZrH $_{2}$ Mg(BH $_{4}$ ) $_{2}$ and F82H TiH $_{2}$ and F82H water and F82H.

Language	:	English
Journal	:	Fusion Engineering and Design
Volume	:	81
Number	:	8-14
Pages	:	p.1285 - 1290
Publication Year/Month	:	2006/02
Meeting title	:	7th International Symposium on Fusion Nuclear Technology (ISFNT-7)
Held date	:	2005/05
Location (city)	:	Tokyo
Location (country)	:	Japan
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.1016/j.fusengdes.2005.09.060
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	Borohydride; Mg(BH $_{4}$ ) $_{2}$ ; Metal Hydride; ZrH $_{2}$ ; Radiation Shielding; Fusion Reactor; TiH $_{2}$ ; F82H; Radioactive Waste; Transport Calculation
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:	Compact Fusion Reactor Using Advanced Shield Materials; Application of Hydrogen-Rich Hydride to the Shield of Fusion Reactor[/]
Cooperating Institute	:

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Registration No. : B20042058
JAEA Abstracts No. : 34000660
Paper Submission No. : 797

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