Published April 30, 2009 | Version v1
Journal article

Advanced neutron shielding material using zirconium borohydride and zirconium hydride

  • 1. Division of Tokamak System Technology, Department of Fusion Facilities, Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801-1 Mukouyama, Naka, Ibaraki 311-0193 (Japan)
  • 2. Institute for Materials Research, Tohoku University, 2-1-1 Katahira, Sendai 980-8577 (Japan)

Description

Neutron transport calculations have been carried out to assess the capability of zirconium borohydride (Zr(BH4)4) and zirconium hydride (ZrH2) as advanced shield materials, because excellent shields can be used to protect outer structural materials from serious activation. The neutron shielding capability of Zr(BH4)4 is lower than ZrH2, even though the hydrogen density of Zr(BH4)4 is slightly higher than that of ZrH2. High-Z atoms are effective in neutron shielding as well as hydrogen atoms. The combination of steel and Zr(BH4)4 can improve the neutron shielding capability. The combinations of (Zr(BH4)4 + F82H) and (ZrH2 + F82H) can reduce the thickness of the shield by 6.5% and 19% compared to (water + F82H), respectively. The neutron flux for Zr(BH4)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.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2008.12.073

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2008.12.073;
PII
S0022-3115(08)00820-9;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
386-388
Journal Page Range
p. 119-121
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
13. international conference on fusion reactor materials
Dates
10-14 Dec 2007
Place
Nice (France)

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.