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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
2020 Winter Meeting and Nuclear Technology Expo
November 15–19, 2020
Chicago, IL|Chicago Marriott Downtown
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Nuclear Science and Engineering
Fusion Science and Technology
NEA issues call to action in report on nuclear cost reductions
A new report from the Paris-based OECD Nuclear Energy Agency declares that nuclear power is needed for countries to meet their Paris Agreement decarbonization and energy security policy goals, but that governmental support for a rapid reduction in the cost of new nuclear capacity through the creation of certain policy frameworks is likely necessary.
Teruya Tanaka, Hiroaki Muta, Yoshimitsu Hishinuma, Hitoshi Tamura, Takeo Muroga, Akio Sagara
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 705-710
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST15-110
Articles are hosted by Taylor and Francis Online.
Performance and applicability of hydride shielding materials are investigated in the helical reactor FFHR-d1 design. Performance of ZrH2 and TiH2 in fast neutron shielding are close to that of WC, which is most effective among candidate materials, for both in-vessel and out-vessel use. The investigation confirms that neutron shielding performance of a two-layered ferritic steel (FS)/ZrH2 or TiH2 shield is similar to that of a one-layered ZrH2 or TiH2 shield with the same total thickness. This shielding property is an important feature to maintain consistency with the structure design of FFHR-d1. In attenuation of direct neutrons from the core plasma in a bending duct, the hydride duct walls show superior performance compared with FS + B4C and WC duct walls. While controls for temperature (at <300 °C) and hydrogen concentration in the coolant gas would be required particularly for in-vessel use, the lower weight densities and quick decay of contact dose rates compared with other candidate materials would be reasons to select these hydride shielding materials.